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Spent Fuel Storage Status and
Future Management in Korea
2008. 10. 20
Seong Won Park, Jin-Mok Hur, Hansoo Lee
Korea Atomic Energy Research Institute
2
Table of Contents
1. Energy Status in Korea
2. Accumulation of Spent Fuel
3. Issues of Proven Options
4. Requirements of Advanced Fuel Cycle
5. Promising Fuel Cycle Concept (KIEP-21)
6. Reference Flowsheet of Pyroprocess
7. Challenges of Pyroprocessing Technology
8. Recent KAERI Efforts
9. Conclusion
3
Energy Consumption World Rank 9th
Oil ConsumptionWorld Rank 7th
Oil ImportWorld Rank 4th (2.7 mb/day)
Energy Status in Korea
Year 2007
Total energy imports in 2007$94.5 bn
(25% of total exports)
BP Statistics of World Energy 2007
96.7% of primary energy sources were imported in 2007.
Self-
suffi
cien
cy [%
]
Korea Japan Germany France U.S. U.K. Canada
20 1939 50
70
87
148
2 427
7
61
78
139
0
20
40
60
80
100
120
140
160
Energy self-sufficiency (without nuclear power)Energy self-sufficiency (including nuclear power)
Energy Balance of OECD Countries 2004-2005 (IEA)
4
<Oil Prices>http:/www.oilnergy.com
Ener
gy Im
port
s ($
bn)
Ener
gy Im
port
s/To
tal I
mpo
rts
(%)
Year
2003 2004 2005 2006 2007 2008 20090
20
40
60
80
100
120
140
160
0
5
10
15
20
25
30
35
Impact of Fuel Prices on Korean Economy
<Coal Prices>http:/www.eia.gov
(1-6)
5
OECD Factbook 2008 : Economic, Environmental, and Social Statistics
Increase in CO2 Emission (1990 vs. 2005)
0.00 0.50 1.00 1.50 2.00 2.50
China
Korea
India
Brazil
Spain
South Africa
Canada
United States
Japan
Italy
United Kingdom
Poland
Germany
Russian Federation
World Total
6
20 units in operation16 PWRs (6 OPR1000)
4 PHWRs (CANDU)
6 units under construction4 OPR1000
• Shin-Kori : ’05.1 ~• Shin-Wolsung : ’05.10 ~
2 APR1400• Shin-Kori : ’07.9 ~
2 units under preparation2 APR1400
• Shin-Ulchin
Basic National Energy Policy (2008. 8. 27)
Current Policy(By 2020)
Nuclear share
36% (2007) → 59% (2030)
▶ About 10 units more by 2030
New Policy(By 2030)
7
Year
Spen
t Fue
l Aris
ings
(1,0
00tH
M)
Major Obstacle for Promoting Nuclear Power
0
10
20
30
40
50
60
70
80
90
100
2005 2015 2025 2035 2045 2055 2065 2075 2085 2095
PWR
CANDU
New Plan
Existing Plan( PWR+CANDU )
100,000 t = 1,000 km in length
8
Acc
umul
atio
n of
Spe
nt F
uel (
10K
tone
s)
Required Capacities for Storage and Disposal
1980 2000 2020 2040 2060 2080 2100
2
34,000 (PWR)
4,000 (PWR)
36,000 (PWR/CANDU)
20,000 (PWR)
1
2
# AFR
HLW Repository#14,000 (CANDU)
44,000 (CANDU)
Direct disposal after AFR
Considering current program for AR expansion
Assuming AFR after 2016 for SF exceeding AR capacity
0
1
2
3
4
5
6
7
8
9
10
11
20,000 (PWR)3
20,000 (PWR) 4
9
Concerns about enormous amount of spent fuel inventory- About 110,000 tHM by 2100 (exceeding 1,000 tHM of annual discharge from 2023)- Concerns about the safety and security of frequent cask transports
Concerns about securing sites for interim storage- Failure in securing AFR sites during past 20 years- Reference case for supporting local community for low-level waste repository- Bad influence from PRs for securing Kyungjoo site for low-level waste repository
Ethical concerns- Avoid placing the responsibility of dealing with nuclear waste on the younger generation - Necessity of desperate efforts on finding better solutions for ultimate disposition
Concerns about promotion of long-term national nuclear power program- Concerns about public acceptance of nuclear program without providing solutions for spent fuel management issue
- Serious setback of national policy on energy security and reduction of CO2 emission
AFR for near-term solution- Difficulty in securing AFR site without any provision of a solution for ultimate spent fuel disposition
Issues of Long-term Interim Storage
10
Issues of Alternative Options
Direct Disposal- Buffer temp. < 100 ℃⇒ 5 kgHM/m2 - Radiotoxicity > 300,000 yrs
PUREX & HLW Disposal- Reduction of repository space : 20~50%- Proliferation risk- High expenses
11
Backfill
Canister
Buffer
Canister
Korean Reference Disposal Concept
Disposal Density- PWR ∼ 5 kg/m2
- CANDU ∼ 26 kg/m2
Required Site Area (PWR SF 100,000 t)- Disposal vault area : 20 km2
- Considering exclusion area : 30 km2
- Considering major faults : 60 km2 (???)
12
Requirements of Advanced Fuel Cycle
Reduction of heat load > 99%(Required repository space < 1/100)
Minimization of Repository Space
Reduction of radiotoxicity < 500 yrs
Reduction of Environmental Burden
1-2 mills/kWh
“Dirty fuel, clean waste”with homogeneous recycling of all TRUs
Enhancement of Proliferation Resistance
Economic Compatibility with the Current Options
Combination of Pyroand
FR meets all criteria
13
Korean, Innovative, Environment-Friendly, and Proliferation-Resistant System for the 21st C (KIEP-21)
Benefits Saves disposal space by a factor of 100Shortens the management period to a fewhundred yearsIncreases U utilization by a factor of 100Ensures intrinsic proliferation resistance
Promising Fuel Cycle Concept (KIEP-21)
FR Closed Fuel Cycle Volume Reduction
GEN-IVFR(SFR)
PWR
CANDU
FR Metal Fuel(U-TRU-Zr)
(Cs, Sr)Decay Storage
DisposalDisposal
S /G
IH T S P ip in g
S e c o n d a r y E M P u m p
R e a c to r C o r e
P r im a r y P u m p
R e a c t o r V e s s e l
IH X
D H X
R e a c t o r H e a d
C o n ta in m e n t V e s s e l
S /G
IH T S P ip in g
S e c o n d a r y E M P u m p
R e a c to r C o r e
P r im a r y P u m p
R e a c t o r V e s s e l
IH X
D H X
R e a c t o r H e a d
C o n ta in m e n t V e s s e l
Recycling
Wastes
Pyroprocess
14
SFRSFR PyroPyro--processprocess
HLWHLWDisposalDisposal D&DD&D
Improvement of economics & safetyMetal fuelConceptual designof advanced SFRby 2016Construction of prototype/demoreactor by 2028
S /G
IH T S P ip in g
S e c o n d a ry E M P u m p
R e a c to r C o re
P rim a ry P u m p
R e a c to r V e s s e l
IH X
D H X
R e a c to r H e a d
C o n ta in m e n t V e s s e l
S /G
IH T S P ip in g
S e c o n d a ry E M P u m p
R e a c to r C o re
P rim a ry P u m p
R e a c to r V e s s e l
IH X
D H X
R e a c to r H e a d
C o n ta in m e n t V e s s e l
Geological disposalsystem Reference TSPAsystemDemonstration ofEBS performanceby 2016Support of disposalsite determination(2030)
Electrolytic reduction& electrorefiningSafeguardsEng-scale pyro-process by 2016Operation of proto-type pyro facilityby 2025
Advanced D&D andsite restoration tech.Decommissioningof KRR-1&2 anduranium conversionfacility by 2010Decommissioning ofcommercial reactors(2030)
Major R&D Projects in KIEP-21
15
C. H. Bean and M. J. Steindler, National Program for Pyrochemical and Dry Processing of Spent Reactor Fuel, Actinide Separations, ACS Symposium Series 117, 1980
Advantages of Pyro-technology (ANL)
Nonproliferation attributes- Fissile components are contaminated by residual fission products and actinides, thereby reducing access
to the material and increasing detectability of diversion (satisfies self-protection criteria).- Close-coupling of relevant facilities reduces reliance on transportation in the fuel cycle.- Need for extensive inventory of spent fuel in storage is minimized.
Processes applicable to various fuels, fuel cycle, and breeder reactor typesFavorable economics
- The economics of small scale reprocessing facilities favors pyroprocessing because of the concentration of material.
- The capability for processing short-cooled fuel reduces the turnaround time in the fuel cycle as well as theinventory cost.
- The elimination of conversion steps at the head end and for the final product may reduce the overall processing cost.
Minimum waste handlingSound resource utilization
- Plutonium can be safely recycled without the risk of proliferation, instead of being discarded.- Rapid recycling of short-cooled fuel reduces the total demand for fissile material in the fuel cycle.
Product amenable to fabricationMinimal of safeguards
- Processes may require very few or no added safeguards, except for protection from sabotage.
Process is exportable- Due to the proliferation-resistant processing, compactness of the plant, and minimal safeguards,
pyroprocessing is exportable.
16
SCSC--1: Selective Crystallization1: Selective CrystallizationSCSC--2: Air Oxidation/Precipitation2: Air Oxidation/Precipitation
Hulls Waste Salt
Uranium
Waste Salt
Cs/Sr
Cutting VoloxidationGranulation
ElectrolyticReduction
Cleaningby SC-1
Electro-Refining
Electro-Winning
U/TRU/ZrFuel
Cleaningby SC-2
DecayStorage
Cd Distil.
U/Zr
RE
Immobil.
Storagefor Reuse
Cleaningby ZrCl4
Off-GasTrapping
GEN-IVSFR
S /G
IH T S P ip in g
S e c o n d a ry E M P u m p
R e a c to r C o re
P rim a ry P u m p
R e a c to r V e s s e l
IH X
D H X
R e a c to r H e a d
C o n ta in m e n t V e s s e l
S /G
IH T S P ip in g
S e c o n d a ry E M P u m p
R e a c to r C o re
P rim a ry P u m p
R e a c to r V e s s e l
IH X
D H X
R e a c to r H e a d
C o n ta in m e n t V e s s e l
MeltingPackaging
Reference Flowsheet of Pyroprocess
17
LaboratoryCommercialDemonstration
490 te (??)230 te (UREX+)Waste Generation2)
(HLW)
Batch TypeContinuous TypeOperation Mode
No [ U + TRUs ]Yes Pure Pu Separation
LowHighCriticality Hazard
< 1 year> 5 yearsCooling Time
< 20About 180No. of Components1)
[Compactness]
PyroprocessPUREX ProcessImprovement in reactor system
- High-throughput reactor system - Corrosion-resistant materials including
electrodes
Optimization of secondary waste treatment process- Recycling of used salts- Waste form integrity
Enhanced safeguardability- Near real-time accounting- Safeguards by design
Ensuring technical & economic viability- Process modeling & simulation- Integrated engineering-scale demonstration
1) H. Tanaka, et al., “Design Study on Advanced Reprocessing System for FR Fuel Cycle,”Global-2001, September 2001, Paris.
2) USDOE, AFCI Comparison Report, May 2005 [Basis: 2,000 MT of Spent Fuel].
Challenges of Pyro-technology
18
To achieve high throughput- Continuous-type voloxidizer- High-efficiency electrolytic reduction system- Continuous-type electrorefiner and cathode processor
To optimize secondary waste treatment process- Cleaning and recycling of used salts- High-integrity waste form
To simplify process design- Harmonization between reactor systems- Alternative process studies
To enhance safeguardability- Neutron counter for nondestructive assay of fissile materials- Close collaboration with IAEA (MSSP)
To prove technical & economic viability- Engineering-scale mock-up design- Pre-conceptual design and cost analysis
Recent KAERI Efforts
19
Objective- To develop a long-term HLW management system and
a complete safety & performance assessment methodology
Key R&D Areas- Long-term management system for all types of HLW- Provision of national HLW management program - Validation of barriers with the KURT operation- Establishment of multi-discipline safety assessment method
Current R&D Activities & Future Action Plan
’07 ’10 ’20’15
* KURT: KAERI Underground Research Tunnel
R&D on HLW Disposal
Validation of Disposal System and TSPA
Validation of Disposal System and TSPA
EBS System Evaluation
EBS System Evaluation
Technologies for CANDU/HANARO SFand HLW from Advanced Fuel Cycle
Technologies for CANDU/HANARO SFand HLW from Advanced Fuel Cycle
Multiple Discipline PA System
Multiple Discipline PA System
KURT OperationKURT Operation Support forSupport forCommercialCommercial
SitingSiting
20
KAERI Underground Research Tunnel
Access Tunnel Access Tunnel
KURT PortalKURT Portal
-- Length: 255 mLength: 255 m-- Access: 180 mAccess: 180 m-- Research module: 75 mResearch module: 75 m
-- Rock mass: graniteRock mass: granite-- Rock support: Lining,Rock support: Lining,
shotcreteshotcrete, rock bolt, rock bolt-- Operation from 2007 onwardOperation from 2007 onward
Research Module Research Module
21
Conclusions
●● KAERI is developing the KAERI is developing the pyroprocessingpyroprocessingtechnology as one of the options for the effective technology as one of the options for the effective
management of spent fuel and is planning to management of spent fuel and is planning to evaluate the technical and economic viability of this evaluate the technical and economic viability of this
technology through engineeringtechnology through engineering--scale scale demonstration.demonstration.
● Nuclear energy is a promising option for
addressing global warming and
exhaustion of fossil fuels.
●● For nuclear energy to For nuclear energy to continuously extend its continuously extend its
future role in the Korean future role in the Korean energy mix, proper energy mix, proper
management of spent management of spent fuel is extremely fuel is extremely
important.important.
● Pyroprocessingtechnology,
compatible with the Goals of GEN-IV nuclear
energy system, offersmany advantages in
this regard.
●● KAERI is also
KAERI is also
developing the HLW
developing the HLW
disposaldisposal
technology that can
technology that can
fit well with the
fit well with the
future fuel cycle options.
future fuel cycle options.
22
Innovation for Next Generations
- Transparent, Innovative, and Environmentally Friendly -
- Thank you for your attention -
