Skills in the field of tritium management CEA/DEN/DTN/STPA/LIPC

1. Skills in the field of tritium managementCEA/DEN/DTN/STPA/LIPC

2. General overview of CEA/DTN tritium activities in the field of fusion CEA PPCS DEMO ITER JET

3. General overview of CEA/DTN activities in the field of fusion CEA/DTN • Expertise on: • T management • T transfer • Tritiated waste handling • Design and process development • Conception • Process Modeling • General integration and scale-up • Safety studies • He purification systems • Experimental development(loops & lab scale) • Analysis /Characterization • Sample characteristics: • T Activity < 3 GBq/sample • up to 20g of Be • containing T, Be and other radionuclides

4. Theoretical : Conceptual design, general integration and scale-up Process simulation using modeling tools (comsol, matlab, prosim, prophyplus…) Process optimization (in terms of energetic approach, yields and technology) Venting system and atmosphere treatment Waste processes for decategorisation Purification and management of Helium, used as coolant Application : Conceptual design and general integration for an non active He purification system (HPC loop, up to 20g/s; 80bar) Focus on conceptual skills: from laboratory to pilot or industrial scale

5. Tritium activity measurement in: Concrete, metals, graphite, soft housekeeping, organic liquid, scintillated cocktails, Be matrices… Development and optimization of processes Detritiation methods (thermal, chemical, mineralization under O2…) Waste decategorisation studies Tritium traps Online tritium measurement and speciation Experimental conditions and limitations: Tritium activity up to 3 GBq/sample Up to 20g of Be Possibility to treat sample containing other radionuclides Focus on laboratory experimental tools

6. Since long time, safety activities for ITER Relation with French nuclear safety authority Relation with French National Radioactive Waste Management Agency (ANDRA) Knowledge of French or European safety constraints Pressurized equipment (97/23/CE) Venting system (ISO 17873) Knowledge of Hazard and Operability studies (HAZOP) Safety analysis (Mosar method) Focus on safety skills • Example: • Application to Venting and gas detritiation system designs for tritium building and hot cells

7. In the field of tritium management, CEA/DTN can handle: Conceptual design studies Process development and modeling Scale-up studies Samples characterization (T and other radionuclide with or without Be) Safety analysis taking into account European and French constraints To conclude…

8. Role of microstructure and heat treatments on the desorption kinetics of tritium from austenitic stainless steelsJournal of Nuclear Materials, Volume 360, Issue 2, 1 February 2007, Pages 177-185J. Chêne, A.-M. Brass, P. Trabuc, O. Gastaldi Influence of heat treatments on residual tritium amount in tritiated stainless steel wasteFusion Engineering and Design, Volumes 75-79, November 2005, Pages 731-735A. Lassoued, J. Chêne, A.-M. Brass, O. Gastaldi, P. Trabuc, G. Marbach Impurities and oxygen control in lead alloysJournal of Nuclear Materials, Volume 301, Issue 1, February 2002, Pages 53-59J. -L. Courouau, P. Trabuc, G. Laplanche, Ph. Deloffre, P. Taraud, M. Ollivier, R. Adriano, S. Trambaud Waste management within the framework of ITER in CadaracheFusion Engineering and Design, Volume 69, Issues 1-4, September 2003, Pages 531-536S. Rosanvallon, S. Nordlinder, L. Fayette, G. Brunel Mitigation of the hydrogen risk in fusion facilities: the first experimental resultsFusion Engineering and Design, Volume 69, Issues 1-4, September 2003, Pages 585-591C. Maruéjouls, E. Bachellerie, C. Latgé, A. Laurent, J. M. Le Lann, J. C. Robin, S. Rosanvallon Analysis of an in-service rupture of the inner first wall of tore supraFusion Engineering and Design, Volumes 56-57, October 2001, Pages 445-449R. Mitteau, P. Chappuis, G. Martin, S. Rosanvallon Some relevant experience

9. Clearance, recycling and disposal of fusion activated materialFusion Engineering and Design, Volume 54, Issues 3-4, April 2001, Pages 635-643M. Zucchetti, R. Forrest, C. Forty, W. Gulden, P. Rocco, S. Rosanvallon Steel detritiation, optimization of a processFusion Engineering and Design, Volumes 51-52, November 2000, Pages 605-609S. Rosanvallon, G. Marbach, A. M. Brass, J. Chêne, J. P. Daclin Lead–lithium eutectic material database for nuclear fusion technologyJournal of Nuclear Materials, Volume 376, Issue 3, 15 June 2008, Pages 353-357E. Mas de les Valls, L.A. Sedano, L. Batet, I. Ricapito, A. Aiello, O. Gastaldi, F. Gabriel A 2D finite element modeling of tritium permeation for the HCLL DEMO blanket moduleFusion Engineering and Design, Volume 82, Issues 15-24, October 2007, Pages 2204-2211F. Gabriel, Y. Escuriol, F. Dabbene, O. Gastaldi, J.F. Salavy, L. Giancarli JET contributions to ITER technology issuesFusion Engineering and Design, Volume 81, Issues 1-7, February 2006, Pages 149-154C.Grisolia, S. Rosanvallon, P. Coad, N. Bekris, J. Braet, D. Brennan, B. Brichard, G. Counsell, C. Day, J. Likonen, G. Piazza, C. Poletiko, M. Rubel, A. Semerok and JET-EFDA Contributors + several EFDA Tasks… Some relevant experience