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.
IAEA 2001