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TUumlV SUumlD TUumlV SUumlD
Interim Storage of Nuclear Waste
Seminar on regulations and technology of waste management and disposal in Germany
March 28th 2018 in Taipei
Dr J Shang
Slide 1
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 2
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 3
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Waste classification scheme by IAEA
Source IAEA
Slide 4
TUumlV SUumlD
Waste classification scheme by IAEA
1
2
3
4
5
6
Source IAEA
Slide 5
TUumlV SUumlD
1
2
3
4
5
6
Summary final storage casks container
A0
1000
9T128T127T126T125T124T123T122T12T12A0
A0
Source IAEA GNS
Konradreg
Slide 6
TUumlV SUumlD
The decline of activity
Slide 7
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 11
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 2
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 3
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Waste classification scheme by IAEA
Source IAEA
Slide 4
TUumlV SUumlD
Waste classification scheme by IAEA
1
2
3
4
5
6
Source IAEA
Slide 5
TUumlV SUumlD
1
2
3
4
5
6
Summary final storage casks container
A0
1000
9T128T127T126T125T124T123T122T12T12A0
A0
Source IAEA GNS
Konradreg
Slide 6
TUumlV SUumlD
The decline of activity
Slide 7
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 11
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 3
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Waste classification scheme by IAEA
Source IAEA
Slide 4
TUumlV SUumlD
Waste classification scheme by IAEA
1
2
3
4
5
6
Source IAEA
Slide 5
TUumlV SUumlD
1
2
3
4
5
6
Summary final storage casks container
A0
1000
9T128T127T126T125T124T123T122T12T12A0
A0
Source IAEA GNS
Konradreg
Slide 6
TUumlV SUumlD
The decline of activity
Slide 7
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 11
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Waste classification scheme by IAEA
Source IAEA
Slide 4
TUumlV SUumlD
Waste classification scheme by IAEA
1
2
3
4
5
6
Source IAEA
Slide 5
TUumlV SUumlD
1
2
3
4
5
6
Summary final storage casks container
A0
1000
9T128T127T126T125T124T123T122T12T12A0
A0
Source IAEA GNS
Konradreg
Slide 6
TUumlV SUumlD
The decline of activity
Slide 7
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 11
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Waste classification scheme by IAEA
1
2
3
4
5
6
Source IAEA
Slide 5
TUumlV SUumlD
1
2
3
4
5
6
Summary final storage casks container
A0
1000
9T128T127T126T125T124T123T122T12T12A0
A0
Source IAEA GNS
Konradreg
Slide 6
TUumlV SUumlD
The decline of activity
Slide 7
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 11
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
1
2
3
4
5
6
Summary final storage casks container
A0
1000
9T128T127T126T125T124T123T122T12T12A0
A0
Source IAEA GNS
Konradreg
Slide 6
TUumlV SUumlD
The decline of activity
Slide 7
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 11
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
The decline of activity
Slide 7
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 11
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 11
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of radioactive waste （LLW-ILW-HLW）
bull Interface interim storage ndash final storageLicences of transport container stores generally for 40 yearsfrom the first storagebull Transport container store Gorleben until the end of 2034 site
interim store individually e g Lingen until 2042bullWaste treatment center and storage on site of NPP amp center
storagesRepository Konrad Commissioning 2022
Repository Site Selection Act (StandAG) dated July 20 2017
bullConstruction of a receiving store at final storage site necessarybull Existing safety cases have been provided for 40 yearsbull Final storage beyond the presently authorised periods could
become necessary for a series of casks
Slide 12
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Conditioning of radioactive waste
SAL
(Storage of
conditioned waste)
SIG
(Social and
infrastructure building)
RBZ
(Treatment of
radioactive waste)
Source EnBW Kernkraft GmbH
Slide 13
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Conditioning of radioactive waste
Size of the building
ca 46m x 76m x 16mSource EnBW Kernkraft GmbH
Slide 14
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Remotely controlled removal of a drum from single-shielded
storage using the 50 kN crance in the reloading cell in the
interim storage
Slide 15
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHReplacement of the container lid on a container filled with concrete
Slide 16
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Interim storage for waste products generating heat (storage bunker L563)
Small picture stacked 200 l drums in a storage cell of the storage bunker(38 m x 35 m x 105 m)
Slide 17
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbH
Casting facility LP30 in storage building D of the interim storage II
(max 2 x 12 containers can be positioned and casted consecutively)
Slide 18
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Facilities for treatment and interim storage
Source WAK GmbHInterim storage II at the beginning of the storage process
Slide 19
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Closed fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation transport(s) reprocessing and recycling of plutonium and uraniumfinal storage of unusable residual materials e g vitrified fission productsolutions
Once-through fuel cycle
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) transport if necessary conditioning (e g repackaging of the fuel elements) direct final storage of disused fuels
ldquoWait and seerdquo strategy
supply of fuel for use in a nuclear power plant fuel cooling installation possibly transport interim storage (local or central) (to be determined)
Slide 20
Strategies of nuclear waste management （HLW）
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example CLAB Sweden
Slide 21
Quelle Svensk Kaumlrnbraumlnslehantering AB
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example ldquoStorage Vaultrdquo Paks Hungary
Slide 22
Source PURAM Interim Storage of Irradiated Fuel (ISIF) 2010
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example NUHOMSreg USA
Slide 23
Source AREVA North America
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Example MAGNASTORreg ndash Concretesteel packaging USA
Slide 24
Quelle NAC International
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
MACSTORreg silo storage Canada
Slide 25
Quelle M Petrovic J Hashmi P Eng Single storage canister to
MACSTOR ndash 14578 Canadian solution and experience in
responsible spent fuel management regin WM2014 Conference
Phoenix Arizona USA March 2ndash6 2014 (2014)
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Nuclear waste management in Germany
Slide 26
Status of interim storage in Germany
Central interim
storage
Site interim
storage
Interim storageIn
operation
since
stored
vessels
(31122014)
TotalAround 850 casks will still be added until the final exit from
the nuclear energy of Germanycopy GRS
Interim Storage Vessels In Operation
since
TBL Ahaus 329 June 1992
TBL Gorleben 113 April 1995
Lubmin 78 Nov 1999
AVR Juumllich 152 August 1993
Biblis KWB 74 18052006
Brokdorf KBR 29 05032007
Brunsbuumlttel KKB 11 02052006
Emsland KKE 38 05042007
Grafenrheinfeld KKG 21 27022006
Grohnde KWG 30 27042006
Gundremmingen KGG 48 25082006
Isar KKI 35 12032007
Kruumlmmel 29 14112006
Neckarwestheim GKN 53 10122002
Philippsburg KKP 58 06122006
Unterweser KKU 27 19032007
Lingen KWL 32 18062007
Total 1157
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Dry spent fuel storage
Castor V19
About 6 m height
Weight about 108 t empty
Costs over 1 million Euro
19 PWR Fuel Elements can be stored
Loading and leak tightness tests can take several weeks
Loaded Casks are inspected by Euratom Inspectors
Source GNS
Slide 27
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Nuclear waste management in Germany
Slide 28
Secondary Lid
Pressure Switch
Neutron Shielding
He Positive Pressure 6 bar
Primary Lid
He Negative Pressure 05 bar
Source GNS
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 29
Protection Lid
Secondary Lid
He-Filling
Neutron Shielding (PE)
Primary Lid
Trunnions for Handling and Tie-Down
Nodular Cast Iron Shell
Neutron Shielding
Trunnions for Handling
Cooling Fins
Wall thickness ca 420 mm
Loaded Weight max 130 t copy GNS
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Nuclear waste management in Germany
Slide 30
Interim storage concepts in Germany
Concept
Concept
Conceptair inletair
inlet
Inlet air
Exhaust air
Source GRS
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Waste management
Interim storage
TUumlV SUumlD Slide 31210318
Interim storage for spent fuel (examples)
Castors in interim storage copy wwwzeitde
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 32
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Requirements on the design of a transportation and storage vessel
bull Inclusion of the radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Safe handling and safe transportation
Nuclear waste management in Germany
Slide 33
Source GNS
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Safety requirments and long-term safety case
Folie 3421032018
License Procedure
Standards for precaution against hazards has to be proved
General - Atomic Energy Act
- ESK Guidelines for dry storage of spent fuel and heat generating radioactive waste in
casks
- hellip
Radiation Protection - KTA 13022 3602 3603
Seismic Events - KTA 2201
Flooding - KTA 2202
Lifting Devices - KTA 3102 3903
Communication - KTA 3901
Fire Protection - KTA 21011 DIN 4102
Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201
Operation - KTA 1201 1202 1404 1401
hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Slide 35
Interface interim storage ndash final storage
Licenses of transport container stores generally for 40 years from the first storageTCS Gorleben until the end of 2034 site interim storage facility individually e g Lingen until 2042
Repository Site Selection Act (StandAG) dated July 20 2017
Commission Underground
investigationSite decision
Construction
Commissioning
Construction of a receiving store at final storage site necessary
Existing safety cases have been provided for 40 yearsFinal storage beyond the presently authorised periods could become necessary for a series of
casks
No world-wide practical experiences with interim storage and transport exceeding the periods
valid in Germany
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interface interim storage ndash final storage
End of interim storage phase rarr evacuation of the interim store anddecommissioningbull (rarr transport) rarr conditioning (rarr transport) rarr final storagebull Details depend on the waste management and the sites selection
Conditioningbull Cask modification (e g filling welding hellip) bull Repackaging of the inventories into repository casks production of
repository bundlesbull Typically hot cell needed for handling
Final storagebull Operating phase with storage processesbull After-closure phase (without maintenance)
Permanent guarantee that protection goals will be met is necessarybull Extensive integrity of inventoriesbullManageability of inventories andor bundlesbull Transportability of inventories andor bundles
Slide 36
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste cask types
Slide 37
14 cask types of different designs used at present
bull 113 pieces with vitrified waste of the reprocessing (HAW)
bull 479 pieces with fuel of experimental demonstration and research reactors
bull Approx 530 pieces with fuel of power reactors (PWR BWR WWER)
Two intact lids together with leakage monitoring are necessary for the
storage
A bdquosealed enclosureldquo is necessary for the transport (primary or secondary
lid)
bull Exception transport HAW 28M is qualified with primary lid only
has to be repaired in case of failure
Traffic regulatory approval
bull Is the precondition for the use of a design for interim storage
bull Approval as type B(U) andor B(U)F package for radioactive materials
bull Based on the requirements of IAEA SSR-6 and the guideline R 003
bull To be renewed periodically
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Special aspects of dry interim storage in casks
Slide 38
High discharge burnups (65 GWdtSM) and use of
MOX fuel
Inventories inside the cask are not directly to access
Verifiability
Permanent transportability of 14 cask types
bull in future probably only one transport process per cask
Traffic regulatory approval has to be maintained
bull cask design approval has to be prolonged
every 3 to 5 years for current cask types
every 10 years for cask types no longer produced
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
Technical Ageing
Slide 39
Causes
bull Neutron and gamma radiation
bull Thermal stress
bull Mechanical stress perhaps due to handling processes
bull Chemical reactions environmental influences
Materials affected
bull Metallic materials
bull Polymerics e g implemented moderator materials made of
polyethylene
bull (Concrete)
Ageing effects
bull Radiation-induced damages
bull Corrosion
bull Changes of material properties
Deformation creeping embrittlement degradation hellip
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
National and international research programs
USA (DoE NRC EPRI) Extended Storage Collaboration Project bull Prolongation of interim storage facilities by means of ageing management
measuresbull Gap analysisbull Used Fuel Disposition Campaignbull DEMO Project (TN-32B)
Storage of high burnup UO2-BE (gt45 GWdMg SM) for 10 years in TN-32B casksInspection of 25 bdquosister rodsldquo for the later determination of modifications
bull Transport and vibration testsJapan
bull DEMO Project planned with 2 fuel elements (48 and 55 GWdtSM) in a test caskbull Staggered duration of 10 50 years with initial and intermediate inspections
National efforts to acquire knowledge (Switzerland Spain) Germany
bull Several workshops of GRS TUumlV hellip e g LTIS workshop Muumlnchen 2013 TUumlV symposium bdquoStorage and transport of radioactive materialsldquo 2015 Coordinated int research programs e g IAEA (SPAR I-III)
Slide 40
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of heat-generating radioactive waste
GRS Research Studies
Burnup inventory and decay calculations to determine the after-power alphaactivities fission gas quantities and similar for UO2- and MOX-fuels including high burnupDevelopment and implementation of adequate cask models to analyse thetemperatures of fuel elements and fuel rods resulting from the data as well as theresulting temperature fields inside the respective caskDevelopment and implementation of a model to determine the hydride solubility in zirconium having regard to that local thermal and mechanical conditions as well asthe shape of zirconium hydride precipitations and their reorientation ratesDevelopment and implementation of a model for cladding creeping in case ofradial oriented zirconium hydrides and of mechanical models to determinetemperature-dependent cladding internal pressure and the hoop stress of thecladding tube in the long-term phaseDevelopment and implementation of a model for determination of Nil ductilitytemperature in case of hydride reorientation as well as comparison of theresults with suitable experimental data of crack and fracture behaviour of fuel-rodcladdingUncertainty analyses
Slide 41
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Equipment for spent fuel handling
Spent fuel handling
Hot Cell workplace
Yellow colour is from the
lead glass
Source Site Restoration Limited
Slide 42
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 43
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
ESK RSK and SSK Guidelines
Slide 44
ESK Nuclear Waste Management Commission
RSK Reactor Safety Commission
SSK Commission on Radiological Protection
ESK advises the BMUB in matters of nuclear waste management
(conditioning interim storage and transport decommissioning and
dismantling of nuclear facilities disposal in deep geological formations)
RSK advises the BMUB in safety-related matters and thus matters
concerning the physical protection of nuclear installations and
radioactive waste management
SSK advises the BMUB on issues concerning the protection from the
risks of ionising and non-ionising radiation
Binding by specification in the license
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Interim storage of spent fuel elements
Slide 45
German regulations for the dry interim storage of spent fuel elements
and heat-generating radioactive wastes
sect 6 AtG in connection with sect 9a AtG
ESK-guidelines
For the dry interim storage of irradiated fuel
elements in casks and heat-generating
radioactive wastes
ESK-guidelines
For the realisation of periodical safety
reviews and the technical aging
management for the interim storage for
irradiated fuel elements and heat-
generating radioactive wastes
Fundamental safety targets
bull Confinment of radioactive inventory
bull Removal of decay heat
bull Warranty of subcriticality
bull Shielding of ionized radiation
bull Avoid unnecessary radiation exposure
Retention license
(currently limited on 40 years)
Operation of interim
storage
Transportation of casks to the
conditioning and final storageSource GRS
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
ESK Recommendations
Slide 46
Guidellines for dry cask storage of spent fuel and
heat generating waste 10June2013
1 Confinement of radioactive material
2 Criticality safety
3 Heat removal
4 Shielding of ionising radiation
5 Radiation protection
6 Structure provisions
7 Technical Installations
8 Accident analysis
9 Self-sufficient operation of the interim storage facility
10 Quality assurance
11 Operation of the interim storage facility
12 Emergency preparedness
13 Periodic safety review
14 Termination of storage
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
ESK Recommendations
Slide 47
Guidellines for execution of periodic safety review and
technical aiging management of dry cast storage of spent
fuel and heat generating waste 13032014
1 Responsibility and period
2 Scope of periodic safety review
3 Results of PSR
4 Technical aiging management
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Harmonization with international regulations
Slide 48
Periodical Safety Review Euratom European Atomic Community
WERA Western European Nuclear Regulators Association
Section 6
Member States shall ensure that the national framework
in place requires licence holders under the supervision
of the competent regulatory authority to regularly
assess and verify and continuously improve as far as
reasonably achievable the nuclear safety of their
nuclear installations in a systematic and verifiable
manner
Safety Reference Level 59
The licensee shall carry out at regular intervals a review
of the safety of the facility (PSR) The review shall be
made periodically at a frequency which shall be
established by the national regulatory framework (eg
every ten years)
Source GRS
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels
bull First version of PSR-guidelines set up in Nov 2010 from ESK
bull Legal basis sect 19a Sec 3 AtG (launched in Dec 2010)
bull Decision BMUB and ESK Test of realization of the guidelines in two chosen interim storages (Gorleben Lingen) before the final implementation
bull Pilot project for the implementation of the PSR-guidelines TBL Gorlebenndash Start in Oct 2011ndash PSR-Report submitted at NMU in May 2013ndash Report of the technical aging management expected in 2016ndash Findings from the pilot project have been entered in the update of the guidelines
bull Updated version of the PSR-guidelines published in March 2014 Basis for the realization of the PSR in further interim storages
Interim storage of spent fuel elements
Slide 49
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
1
Contents
Introduction
2 Concept and technologies
Slide 50
5 Conclusion
3 Safety requirements and long-term safety case
4 Regulations and guildelines
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Conclusion
1 Disposal of nuclear waste
Waste classification scheme by IAEAHWL deep geological disposalILW intermediate depth disposalLLW near surface disposal
2 Interim storage of nuclear waste on Sites
Waste treatment center and interim storage (LLWILW)
Dry storage of spent fuel and vitrified waste(HLW)
3 Safety requirments and long-term safety case
Radiation Protection - KTA 13022 3602 3603Flooding - KTA 2202Lifting Devices - KTA 3102 3903Communication - KTA 3901Fire Protection - KTA 21011 DIN 4102Structural Design - RSK-Guidelines for PWR BMI-Safety Criteria for NPP KTA 2201Operation - KTA 1201 1202 1404 1401
4 Regulation and guildlines
ESK Guidellines for dry cask storage of spent fuel and heat generating waste 10June2013
ESK Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste 13032014
Slide 51
TUumlV SUumlD
Thank you for your attention
Slide 52
TUumlV SUumlD
Thank you for your attention
Slide 52
