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Fusion at SCK•CEN

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

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Fusion at SCK•CEN

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  1. Fusion at SCK•CEN

  2. 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

  3. Belgian Fusion Association 7.7 M€/year (1.6% of European budget) 30% Federal Ministry of Economy 40% European Commission SCK•CEN Federal Ministry of Defence 10% (GRADEL Luxembourg) ERM/KMS ULB KUL 10% French-Community Ministry of Education UCL Flemish Ministry of Education 10%

  4. 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

  5. Most of our activities is focused on radiation effects 3 M€ 40% 40% DIAGNOSTICS and RH: Ceramics, Glass Optical fibres Sensors ITER PFC and HCBP: Be TBM+DEMO: RAFM Divertor/TBM: Cu (W, CFC, Inconel) 20% Waste strategy Socio-economics

  6. 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

  7. Hot cell capabilities • Mechanical testing • Microstructural analysis • Corrosion loops • Reactivity tests

  8. 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

  9. ITER instrumentation: Radiation effects on ceramics and glasses • Insulator • Optical fibres • Cables • Bolometer Remote handling Diagnostics • Optical link • Consultancy for RH unit design • Components for divertor cassettes

  10. SCK•CEN focuses on two crucial questions in waste management Beryllium Tritium “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 Total waste volume: 94,645 tonnes 100 years cooling time Will shallow land disposal suffice? “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”. El Cabril Acceptance Criteria: Without detritiation: 16,841 tonnes rejected With detritiation: 675 tonnes rejected Recycling issue Detritiation issue

  11. Minimising Occupational Radiation Exposure VISIPLAN A 3D ALARA Planning Tool for Nuclear Environments

  12. 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

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