Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Mitsuru Uetake"'
Publikováno v:
Fusion Technology. 34:234-240
The tritium bred in a deuterium-tritium fusion reactor is removed from its blanket by using helium sweep gas mixed with some amount of hydrogen to promote the release rate. From the viewpoint of uptake capacity at the partial pressure of tritium and
Publikováno v:
Journal of Nuclear Science and Technology. 33:492-503
Publikováno v:
Fusion Technology. 28:1738-1748
The tritium bred in a deuterium-tritium fusion reactor is removed from its blanket by using helium sweep gas. From the viewpoint of adsorption capacity and pressure of tritium at release, a cryosor...
Autor:
Ken-ichi Tanaka, Masabumi Nishikawa, Mikio Enoeda, Kenji Okuno, Mitsuru Uetake, Yoshinori Kawamura
Publikováno v:
Fusion Technology. 28:711-716
The effective tritium recovery system should be designed to recover tritium from DT reactor blanket sweep gas in a form easy to transfer to the main fuel cycle. The cryosorption method using a porous adsorbent at the temperature of liquid nitrogen is
Autor:
Yoshinori Kawamura, Masabumi Nishikawa, Kenji Okuno, Mitsuru Uetake, Mikio Enoeda, Ken-ichi Tanaka
Publikováno v:
Fusion Technology. 28:591-596
Experimental results showed that Q2 gas was adsorbed effectively by CMSB on an early stage of breakthrough even though CH4 exists in the inlet gas. Particularly, in the case of Q2 with low concentration of CH4, the break through curve of Q2 showed al
Publikováno v:
Fusion Technology. 28:717-722
Autor:
George Tsotridis, John P. Holdren, Yuzo Fukai, Saša Blagus, Tomoaki Yoshida, Shalom Eliezer, Zohar Henis, Masabumi Nishikawa, Tadasu Takuma, Mitsuru Uetake, Ann P. Kinzig, Ignacio Goded, Masatada Ogasawara, Marijan Vuković, Kenji Yamaji, Michinori Yamauchi, Akiyoshi Hatayama, Paul J. Hibbard, Jiing Dwan Lee, Mladen Bogovac, Antun Drašner, Kunihiko Okano, Ken-ichi Tanaka
Publikováno v:
Fusion Technology. 26:1-4
Publikováno v:
Fusion Technology. 26:17-26
The tritium bred in a deuterium-tritium fusion reactor is to be extracted from the tritium breeding blanket by sweep gas. To be used as fuel for the reactor, the tritium must be recovered in a form that is easy to transfer to the main fuel cycle. The
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Akademický článek
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