Effect of water vapor on tritium permeation behavior in the blanket system

► Tritium bred in the blanket must be effectively recovered to establish the fuel cycle of a fusion reactor. ► We found that coexistence of the amount of water vapor in the purge gas can decrease the tritium recovering ratio. ► Almost no decrease in permeation rate of F82H in the breeding part is ob...

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Veröffentlicht in:	Fusion engineering and design 2012-08, Vol.87 (5-6), p.525-529
Hauptverfasser:	Yamasaki, Hideki, Kashimura, Hideaki, Matsuda, Shohei, Kanazawa, Tatsuhiko, Hanada, Tomoki, Katayama, Kazunari, Fukada, Satoshi, Nishikawa, Masabumi
Format:	Artikel
Sprache:	eng
Schlagworte:	Blanketing F82H Ferritic stainless steels Hydrogen storage Martensitic stainless steels Palladium Palladium base alloys Pd–Ag Penetration Permeation Recovery Solid breeder blanket Tritium Water coexistence Water vapor
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