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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. Hayashi2000年被引用 7Nuclear FusionIF 3出版社

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.

日本語訳

ITERの燃料浄化システムのために、パラジウム拡散器と電解反応器から構成されるシステムが提案され、その後開発された。このシステムの性能は、単体試験において詳細に研究された。ITERの燃料シミュレーションループは、開発された燃料浄化システムと水素同位体分離システムを接続して構築され、ループ内の各システムの機能が実証された。ITERの真空容器のヘリウムグロー放電洗浄中の排気ガスからのトリチウム回収のために、極低温モレキュラーシーブベッドシステムが提案され、実証された。

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