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

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

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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.


PACS

52.55.Fa Tokamaks, spherical tokamaks

52.80.Hc Glow; corona

28.52.Fa Materials

28.52.Cx Fueling, heating and ignition

Subjects

Nuclear physics

Plasma physics

Dates

Issue 3Y (March 2000)

Received 30 November 1998, accepted for publication 19 March 1999



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