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Development of a tritium fuel processing system using an electrolytic reactor for ITER

T. Yamanishi et al 2000 Nucl. Fusion 40 515-518   doi: 10.1088/0029-5515/40/3Y/311  Help

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T. Yamanishi, Y. Kawamura, Y. Iwai, T. Arita, T. Maruyama, T. Kakuta, S. Konishi, M. Enoeda, S. Ohira, T. Hayashi, H. Nakamura, K. Kobayashi, T. Tadokoro, H. Nakamura, T. Ito, M. Yamada, T. Suzuki, M. Nishi, T. Nagashima and M. Ohta
Tritium Engineering Laboratory, Japan Atomic Energy Research Institute, Tokai, Ibaraki, Japan
E-mail: yamanishi@tpl.tokai.jaeri.go.jp

Abstract. A system composed of a palladium diffuser and an electrolytic reactor has been proposed and then developed for the fuel cleanup system of ITER. The performance of the system has been studied in detail in a stand-alone test. A fuel simulation loop of ITER was constructed by connecting the fuel cleanup and hydrogen isotope separation systems developed; and the function of each system in the loop has been demonstrated. For tritium recovery from the exhaust gas during helium glow discharge cleaning of the vacuum chamber of ITER, a cryogenic molecular sieve bed system has been proposed and demonstrated.

Print publication: Issue 3Y (March 2000)
Received 30 November 1998, accepted for publication 19 March 1999

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