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(ITERP2/05) Development of Tritium Fuel Processing System Using Electrolytic Reactor for ITER

T. Yamanishi, Y. Kawamura, Y. Iwai, T. Arita, T. Maruyama, T. Kakuta, S. Konishi, M. Enoeda, S. O'Hira, T. Hayashi, H. Nakamura, K. Kobayashi, T. Tadokoro, H. Nakamura, T. Ito, M. Yamada, T. Suzuki, M. Nishi, T. Nagashima, M. Ohta

Tritium Engineering Laboratory, Japan Atomic Energy Research Institute, Tokai, Ibaraki, 319-1195 Japan

Abstract.  The system composed of a palladium diffuser and an electrolytic reactor was proposed, and was developed for a Fuel Cleanup system of ITER. The performance of the system was studied in a stand-alone test in detail. A fuel simulation loop of ITER was constructed by connecting the developed Fuel Cleanup and Hydrogen Isotope Separation systems; and the function of each system in the loop was demonstrated. For the tritium recovery from the exhaust gas at He glow discharge cleaning of vacuum chamber of ITER, a cryogenic molecular sieve bed system was proposed and demonstrated.

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IAEA 2001