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

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

3. 3 General overview of CEA/DTN activities in the field of fusion CEA/DTN 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 Design and process development Conception Process Modeling General integration and scale-up Safety studies He purification systems Expertise on: T management T transfer Tritiated waste handling

4. 4 Focus on conceptual skills: from laboratory to pilot or industrial scale 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)

5. 5 Focus on laboratory experimental tools 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 O 2 …) –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

6. 6 Focus on safety skills 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) Example: Application to Venting and gas detritiation system designs for tritium building and hot cells

7. 7 To conclude… 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

8. 8 Some relevant experience Role of microstructure and heat treatments on the desorption kinetics of tritium from austenitic stainless steels Journal of Nuclear Materials, Volume 360, Issue 2, 1 February 2007, Pages 177-185 J. Chêne, A.-M. Brass, P. Trabuc, O. Gastaldi Influence of heat treatments on residual tritium amount in tritiated stainless steel waste Fusion Engineering and Design, Volumes 75-79, November 2005, Pages 731-735 A. Lassoued, J. Chêne, A.-M. Brass, O. Gastaldi, P. Trabuc, G. Marbach Impurities and oxygen control in lead alloys Journal of Nuclear Materials, Volume 301, Issue 1, February 2002, Pages 53-59 J. -L. Courouau, P. Trabuc, G. Laplanche, Ph. Deloffre, P. Taraud, M. Ollivier, R. Adriano, S. Trambaud Waste management within the framework of ITER in Cadarache Fusion Engineering and Design, Volume 69, Issues 1-4, September 2003, Pages 531-536 S. Rosanvallon, S. Nordlinder, L. Fayette, G. Brunel Mitigation of the hydrogen risk in fusion facilities: the first experimental results Fusion Engineering and Design, Volume 69, Issues 1-4, September 2003, Pages 585-591 C. 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 supra Fusion Engineering and Design, Volumes 56-57, October 2001, Pages 445-449 R. Mitteau, P. Chappuis, G. Martin, S. Rosanvallon

9. 9 Some relevant experience Clearance, recycling and disposal of fusion activated material Fusion Engineering and Design, Volume 54, Issues 3-4, April 2001, Pages 635-643 M. Zucchetti, R. Forrest, C. Forty, W. Gulden, P. Rocco, S. Rosanvallon Steel detritiation, optimization of a process Fusion Engineering and Design, Volumes 51-52, November 2000, Pages 605-609 S. Rosanvallon, G. Marbach, A. M. Brass, J. Chêne, J. P. Daclin Lead–lithium eutectic material database for nuclear fusion technology Journal of Nuclear Materials, Volume 376, Issue 3, 15 June 2008, Pages 353-357 E. 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 module Fusion Engineering and Design, Volume 82, Issues 15-24, October 2007, Pages 2204-2211 F. Gabriel, Y. Escuriol, F. Dabbene, O. Gastaldi, J.F. Salavy, L. Giancarli JET contributions to ITER technology issues Fusion Engineering and Design, Volume 81, Issues 1-7, February 2006, Pages 149-154 C.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…