fusion at sck•cen
DESCRIPTION
Fusion at SCK•CEN. SCK•CEN. Foundation of Public Utility: created 1952, ~ 600 employees; turn-over ~ 80 M€/yr Reactors : safety, materials, instrumentation, neutronics, new reactors (fusion, ADS) Waste : dismantling, waste disposal, waste characterisation - PowerPoint PPT PresentationTRANSCRIPT
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Fusion at SCK•CEN
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SCK•CEN
• Foundation of Public Utility: created 1952, ~ 600 employees; turn-over ~ 80 M€/yr
• Reactors: safety, materials, instrumentation, neutronics, new reactors (fusion, ADS)
• Waste: dismantling, waste disposal, waste characterisation
• Radiation protection, emergency planning, safeguards, remediation of contaminated sites
• Training: Post-graduate nuclear engineering degree (BNEN)
• Socioeconomic studies, space applications, medical applications
• Facilities: BR2, BR1, VENUS, BR3, HADES, LHMA, Nuclear analysis and chemical laboratories, MYRRHA
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SCK•CEN
ULB
ERM/KMS
Belgian Fusion Association7.7 M€/year
(1.6% of European budget)
KUL
(GRADELLuxembourg)
UCL
30%40%
10%
10%
10%
FlemishMinistry of Education
French-Community Ministry of Education
Federal Ministry of Defence
Federal Ministry of Economy
European Commission
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Fusion Budget at SCK•CEN
• Expenses 3 M€/yr
• Income 1 M€/jaar
• Specific dotation 1 M€/jaar
• 20 equivalent persons-yr• 120 persons involved• 8 departments
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Most of our activities is focused on radiation effects
ITER PFC andHCBP: Be
TBM+DEMO: RAFM
Divertor/TBM: Cu
(W, CFC, Inconel)
DIAGNOSTICSand RH:
Ceramics, Glass
Optical fibresSensors
Waste strategy
Socio-economics
40% 40%
20%
3 M€
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The BR2 in Mola versatile high flux reactor
60-120 MW reactor, Be and light water moderated, 12 bar water cooled, highly enriched fuel (93 and 72%), 40 years of operation in 2002
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Hot cell capabilities
• Mechanical testing
• Microstructural analysis
• Corrosion loops
• Reactivity tests
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Metals under radiation
• Chemical behaviour of pebbles• Mechanical behaviour of irradiated
material• Study of waste conditioning for
disposal
• Mechanical behaviour after irradiation
• Modellisation of radiation effect• Corrosion tests in water and Pb17Li• Study of high temperature
irradiation capabilities• IFMIF design
• In-situ mechanical testing• Erosion-corrosion under incident
heat flux
• Mechanical characterisation after irradiation
Beryllium
Eurofer
Copper
Tungsten, CFC, Inconel
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ITER instrumentation: Radiation effects on ceramics and glasses
• Insulator
• Optical fibres
• Cables
• Bolometer
• Optical link• Consultancy for RH
unit design• Components for
divertor cassettes
Remote handling Diagnostics
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SCK•CEN focuses on two crucial questions in waste management
“All of the waste, after remaining in-situ for some decades, may, if desired, be regarded as non-radioactive or recycled, with no need for repository disposal.” PPCS report 2004
“Waste containing considerable amounts of Be should not to be acceptable for near-surface disposal. Deep disposal of these waste types should therefore be considered”.
Recycling issue
Beryllium Tritium
Total waste volume: 94,645 tonnes 100 years cooling time Will shallow land disposal suffice?
Detritiation issue
El Cabril Acceptance Criteria:Without detritiation: 16,841 tonnes rejectedWith detritiation: 675 tonnes rejected
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Minimising Occupational Radiation Exposure
VISIPLANA 3D ALARA Planning Tool for Nuclear Environments
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Socio-economics
• 2001-2003: Public attitude towards ITER: focus group analysis
• 2001-2003: Sustainability assessment for fusion• 2005-2006: Guidance related to scenario and
modelling exercises • 2005-2006: Attitude towards energy models• 2006: Media analysis and focus group at
Cadarache • 2007: Lessons learned from participative
processes in big nuclear projects