MYRRHA presentation_Status_0ct2013_HAA_28.10.2013.pptx

7/27/2019 MYRRHA presentation_Status_0ct2013_HAA_28.10.2013.pptx

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MYRRHA

Multipurpose hYbrid Research Reactor for High-tech ApplicationsA flexible and fast spectrum irradiation facility

ThEC13, CERN, Geneva (CH)

October 28-31, 2013


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MYRRHAMultipurpose hYbrid Research Reactor for High-tech Applications

A flexible and fast spectrum irradiation facility

Prof. Dr. Hamid At AbderrahimSCKCEN, Boeretang 200, 2400 Mol, Belgium

[email protected] [email protected]
mailto:[email protected]:[email protected]:[email protected]:[email protected]


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MYRRHA - Accelerator Driven System

Reactor Subcritical or Critical modes 65 to 100 MWth

Accelerator(600 MeV - 4 mA proton)

FastNeutronSource

Spallation Source

Lead-Bismuthcoolant

MultipurposeFlexible

IrradiationFacility
http://d/MYRRHA/Images&Figures/MYRRHA_DV-4.avi


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MYRRHA Accelerator Challenge

fundamental parameters (ADS)

particle p

beam energy 600 MeV

beam current 4 mA

mode CWMTBF > 250 h

implementation

superconducting linac

frequency 176.1 / 352.2 / 704.4 MHz

reliability = redundancy double injector

fault tolerant scheme

failure = beam trip > 3 s


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About beam trips


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MYRRHA linacMore on MYRRHA accelerator see paper THOAD09 by Roberto Salemme et al.


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Reactor Vessel Reactor Cover Core Support Structure

Core Barrel Core Support Plate Jacket

Core Reflector Assemblies Dummy Assemblies Fuel Assemblies

Spallation Target Assembly and Beam Line Above Core Structure

Core Plug Multifunctional Channels Core Restraint System

Control Rods, Safety Rods, Mo-99 production units Primary Heat Exchangers Primary Pumps

Si-doping Facility Diaphragm

IVFS IVFHS

IVFHM

Reactor layout

SCKCEN


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Core and Fuel Assemblies

151 positions 37 multifunctional plugs


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Core and Fuel Assemblies

Fuel Cladding in 15-15 Ti Wire wrap Wrapper in T91


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Cooling systems

Decay heat removal (DHR) throughsecondary loops 4 independent loops

redundancy (each loop has 100%capability)

passive operation (naturalconvection in primary, secondaryand tertiary loop)

Ultimate DHR through RVCS

(natural convection)


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Integration into building


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Multipurpose facilityADS demonstration & P&T Research

MultipurposehYbridResearchReactor forHigh-tech

ApplicationsWaste

Fission GEN IV Fusion

Fundamental

research

Silicondoping

Radio-isotopes

50 to 100 MWth

FFast = ~1015 n/cm.s(En>0.75 MeV)

F = 1 to 5.1014 n/cm.s

(ppm He/dpa ~ 10)

in medium-large volumes

Material research

FFast = 1 to 5.1014 n/cm.s

(En>1 MeV) in large volumes

Fuel researchtot = 0.5 to 1.1015 n/cm.s

Fth = 0.5 to 2.1015 n/cm.s

(En


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Motivation for transmutation

spent fuelreprocessing

noreprocessing

Uraniumnaturel

Time (years)

Relativeradio

toxicity transmutation

of spent fuel

Duration Reduction1.000x

Volume Reduction100x


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European Strategy for P&T

The implementation of P&T of a large part of the high-level nuclearwastes in Europe needs the demonstration of its feasibility at anengineering level. The respective R&D activities could bearranged in four buildingblocks:

1. Demonstration of the capability to process a sizable amount of spent fuel fromcommercial LWRs in order to separate plutonium (Pu), uranium (U) and minoractinides (MA),

2. Demonstration of the capability to fabricate at a semi-industrial level thededicated fuel needed to load in a dedicated transmuter (JRC/ITU),

3. Design and construction of one or more dedicated transmuters,

4. Provision of a specific installation for processing of the dedicated fuelunloaded from the transmuter, which can be of a different type than the oneused to process the original spent fuel unloaded from the commercial powerplants, together with the fabrication of new dedicated fuel.


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Fast Neutron are unavoidable for transmutation

To transmute MAs, we need to fission them The ration Fission/Capture is more favorable with fast neutrons


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Proton Beam

Spallation Target

accelerator

Both Critical reactors as well asADScan be used as MAs transmuters

Nevertheless,critical reactors, heavily loaded with MAs, can experience severe safetyissue due to reactivity effect induced by a smaller fraction of delayed neutrons.

ADScan operate in a more flexible and safer manner even ifheavily loaded with MAshence leading to efficient transmutation therefore we say that sub-criticality is not a

luxury but a necessity.

Is sub-criticality a luxury?


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ProtonAccelerator

SubcriticalNeutronMultiplier

SpallationSource

p n

ADS is presently studied for the MAs transmutation dueto their smaller fraction of delayed neutrons and their

impact of the kinetics parameters of the reacteur

235U 650 pcm 238U 1480 pcm238Pu 120 pcm 239Pu 210pcm240Pu 270pcm 241Pu 490 pcm242Pu 573 pcm 237Np 334 pcm241Am 113 pcm 243Am 208 pcm242Cm 33 pcm 244Cm 100 pcm

If one wants to have a heavily

loaded core (>10%), one needs

to considre ADS

Why sub-criticality is needed


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ADS is the most efficient system for burning MAs

MA Production Rate (grams / GWh)Pu Production Rate (grams / GWh)

* Mike Cappiello, (LANL), The Potential Role of Accelerator Driven Systems in the US, ICRS-10/RPS2004, Madeira (PT), 2004


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Even with completely different national NE policiesEuropean solution for HLW works with ADS

Spentfuel A

MOX

Fabrication

UOX

Fabrication

Enriched

U

PWR

MOX

PWR

UOX

Reprocessing

B

Spent

fuel B

Reprocessing

A

ADS

Pu

ADS fuel

fabrication

ADS fuel

reprocessing

Spent fuel

ADS

Pu + MA

Pu + MA

GROUP A

GROUP B

REGIONAL

FACILITIES

MA

Spentfuel A

MOX

Fabrication

UOX

Fabrication

Enriched

U

PWR

MOX

PWR

UOX

Reprocessing

B

Spent

fuel B

Reprocessing

A

ADS

Pu

ADS fuel

fabrication

ADS fuel

reprocessing

Spent fuel

ADS

Pu + MA

Pu + MA

GROUP A

GROUP B

REGIONAL

FACILITIES

MA

Scenario 1 objective: elimination of As spent fuel by 2100A = Countries Phasing Out, B = Countries Continuing

SHARED Advantages for A ADS shared with B ADS burn As Pu&

MA Smaller Fu-Cycle

units & shared

Advantages for B ADS shared with B ADS burn Bs MA As uses Bs Pu (part)

as resource in FR FR fleet not contam

with MAs Smaller Fu-Cycle

units & shared


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Multipurpose facility

MultipurposehYbridResearchReactor forHigh-tech

ApplicationsWaste

Fission GEN IV Fusion

Fundamental

research

Silicondoping

Radio-isotopes

50 to 100 MWth

FFast = ~1015 n/cm.s

(En>0.75 MeV)

F = 1 to 5.1014 n/cm.s

(ppm He/dpa ~ 10)

in medium-large volumes

Material research

FFast = 1 to 5.1014 n/cm.s

(En>1 MeV) in large volumes

Fuel researchtot = 0.5 to 1.1015 n/cm.s

Fth = 0.5 to 2.1015 n/cm.s

(En


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IPS in Chan [0 0 0] IPS in Chan [2 0 0]

Sample n dpa/EFPY tot dpa/EFPY tot

8 18.1 2.38E+15 16.2 2.12E+15

7 23.0 2.85E+15 20.7 2.54E+15

6 25.9 3.19E+15 23.3 2.85E+15

5 27.5 3.37E+15 24.5 3.02E+154 27.2 3.39E+15 24.5 3.03E+15

3 25.7 3.23E+15 22.9 2.89E+15

2 22.3 2.92E+15 19.9 2.62E+15

1 17.3 2.50E+15 15.5 2.23E+15

Material Irradiation Performances for FR ReactorsCritical@100 MW


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MYRRHA-IMIFF for fusion materialMaterial samples loaded in the spallation target vicinity

Core lay-out: Irradiation in sub-critical mode

600MeV proton beam hitting the beam tube, with spallation directlyin reactor coolant LBE, creating high energetic neutrons

Sample holder cooled by He

Sample temperature range: 200C 550C

Sample temperature = controlled


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MYRRHA-IMIFF for fusion material

In sub-critical ADS-mode , a high appmHe/dpa ratiois reached, especially in the region of the window ofspallation source

Volume of 1 lt with appmHe/dpa ~ 12 close tospallation target

Useful volume

30 lt with range from 5 to 20 appmHe/dpa

(Pre-)selection of materials for fusion application


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MYRRHA for fusion irradiations

Estimated damage induced in DEMO and proposed

irradiation conditions in IFMIF and MYRRHA-IMIFF


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Radioisotope (Mo-99) production capabilitySub-critical @ 73 MW

0 100 200 300 400 5000

50

100

150

200

250

300

Spec

ificactivity(Ci/g-

U)

Time (hours)

Mo-99, upper set

Mo-99, central set

Mo-99, lower set

Tc-99m, upper set

Tc-99m, central set

Tc-99m, lower set

Average specific

power

173 W/cm2

184 W/cm2

171 W/cm2


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Radioisotope (Mo-99) production capabilityCritical @ 100 MW

Heat flux 400 W/cm2Plate n Watt/cm

2

1 198.6

2 203.4

3 208.8

4 215.1

5 217.8

6 219.3

7 218.6

8 214.7

9 209.1

10 203.0

11 198.2


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European Context

EnergyIndependenceKnowledgeEconomyESFRIEuropeanStrategicForum forResearchInfrastructure

SET PlanEuropeanStrategicEnergy Plan

27.11.2010Confirmed on ESFRIpriority list projects

15.11.2010in ESNII

(SNETP goals)


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MYRRHA: an international networkwith a large Belgian dimension
http://www.ciemat.es/portal.do


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MYRRHA inspires many Euratom FP projects

TOPIC

FP5

FP6

FP7

Coupling MUSE DM2 ECATS FREYAFuels FUTURE DM3 AFTRA FAIRFUELSMaterials MEGAPIE

DM4 DEMETRAMATTER

SPIRE, TECLA GETMATDesign PDS-XADS DM1 DESIGN CDT

MAXADOPT EUROTRANS SERIM G4

Thermal-Hydraulics ASCHLIM THINS

LFR - ESLY LEADERInfrastructures - VELLA, MTRI3 ADRIANA, SARGEN,

NEWLANCERScenario Studies - PATEROS ARCASSafety - - SEARCH, SILER,

MAXSIMA


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Belgian commitment: securedInternational consortium: under construction

Belgium 60 M(12 M/y x 5 y)

2nd phase (11 y)others 576 M

Belgium 324 M(36 M/y x 9 y)

Consortium


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The project scheduleExecuting presently the FEED Phase: 2010-2014

2010-2014Front EndEngineeringDesign

2019On siteassembly

2016-2018Construction ofcomponents &civil engineering

2015Tendering &Procurement

2020-2022Commissioning

2023Progressivestart-up

2024-Full

exploitation

FEED(Front EndEngineering

Design)

Minimise

technologicalrisks

Secure

the licensing

Secure a

sound

management

and

investment

structure

PDPpreliminarydismantling

plan

PSARpreliminary

safetyassesment

EIARenvironmental

impactassesment

CentralProjectTeam

OwnerEngineering

Team

OwnerConsortium

Group

2010-2014/15


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MYRRHA R&D facilities in TCH

34

COMPLOT

RHAPTER

HELIOSESCAPE

CRAFT

MEXICO

LILIPUT.

LIMETS

HLM Lab

US Lab

INVESTMENT PHASE


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International Members Consortium Phase 1As of early 2012

INVESTMENT PHASE

BE

EU countries

Asian country

EU

ROW

SCKCEN

(on behalf ofBelgianFederal

Government)

EU countryPublic

foundation

Asian country

EU participation

ROW participation

Belgian Federal Ministryof Energy

(50%)

Belgian Federal Ministry

of Science Policy (50%)

40 %

Major European partners

A major Asian partner

EU FP7 (RTD) / SET-Plan (Energy)

ROW

(*) European ResearchInfrastructure Consortium

ERIC (*)Contribution to

investmentcapital

(960 M09)

Participation vehicle

(Consortium members)

Primary

investors IPRmanagement

rules tbd

OPERATION PHASE


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International Members Consortium - Phase 2

OPERATION PHASE

Members of Consortium- Individual research of a member of Consortium- Collaborative research amongst members of

Consortium- 3 years program commitment

CLOSED/SHARED

INFORMATION

for MoC

Open User Facility- Governments funding- Criteria of research excellence- Independant program access committee (PAC)

Collaborative research- Distribution of information to participants

Contract research..Commercial services

- RI- NTD Silicon

~25%

~25%

~25%

~25%

OPENINFORMATION

SHAREDINFORMATION

for participants

CLOSEDINFORMATION

for participants

ERIC (*)

(*) European ResearchInfrastructure Consortium

BENEFITS for Members of Consortium Board position to control overal operation Priority of access Potential benefit of low price (compensation

profit from commercial revenues) Capacity transfer flexibility (rules tbd)

SCKCENas qualified and

licenced operator ofthe MYRRHA

infrastructure undercontractual

arrangement with ERIC


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Conclusions

MYRRHA As a Multipurpose Fast Spetrum irradiationfacility selected by ESFRI, is responding to: The issue of addressing the nuclear waste legacy of present

reactor technology through advance options (ADS, P&T)

The SNETP need for a multipurpose research infrastructure

expressed in its Strategic Research Agenda whatever theconsidered technology for Gen.IV systems

The Objective of Belgium and SCKCEN to maintain a high levelexpertise in the country in the nuclear safety, nuclear technologyand nuclear competencies independently of the future of NE

The objective of the European Commission to make available aseries ofrelevant irradiations facilities for the fusion materialresearch community towards the DEMO construction

Secure society needs for RI for medical applications and Dopped-Si for renewable Energy


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MYRRHA: EXPERIMENTAL ACCELERATOR DRIVEN SYSTEMA pan-European, innovative and unique facility at Mol (BE)

BR2 reactor

(existing)

MYRRHAreactor

building

MYRRHA LINAChigh energy tunnel

ECR source &Injector Building

Utilitiesbuildings

MYRRHA HLM TCH Hall to visit Friday
http://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.movhttp://c/Users/haitabde/Videos/myr010000_Old.mov


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PLEASE NOTE!This presentation contains data, information and formats for dedicated use ONLY and may not be copied,

distributed or cited without the explicit permission of the SCKCEN. If this has been obtained, please reference itas a personal communication. By courtesy ofSCKCEN.

SCKCENStudiecentrum voor Kernenergie

Centre d'Etude de l'Energie Nuclaire

Belgian Nuclear Research Centre

Stichting van Openbaar NutFondation d'Utilit PubliqueFoundation of Public Utility

Registered Office: Avenue Herrmann-Debrouxlaan 40 BE-1160 BRUSSELSOperational Office: Boeretang 200 BE-2400 MOL

Documents

MYRRHA presentation_Status_0ct2013_HAA_28.10.2013.pptx