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Yamanishi, Toshihiko; Hayashi, Takumi; Shu, Wataru; Kawamura, Yoshinori; Nakamura, Hirofumi; Iwai, Yasunori; Kobayashi, Kazuhiro; Isobe, Kanetsugu; Arita, Tadaaki; Hoshi, Shuichi; et al.
Fusion Engineering and Design, 83(10-12), p.1359 - 1363, 2008/12
Times Cited Count：4 Percentile：28.73(Nuclear Science & Technology)At TPL (Tritium Process Laboratory) of JAEA, ITER relevant tritium technologies have been studied. The design studies of Air Detritiation System have been carried out in JAEA as a contribution of Japan to ITER. For the tritium processing technologies, our efforts have been focused on the research of the tritium recovery system of ITER test blanket system. A ceramic proton conductor has been studied as an advanced blanket system. A series of fundamental studies on tritium safety technologies not only for ITER but also for fusion DEMO plants has also been carried out at TPL of JAEA. The main research activities in this field are the tritium behavior in a confinement and its barrier materials; monitoring; accountancy; detritiation and decontamination etc. In this paper, the results of above recent activities at TPL of JAEA are summarized from viewpoint of ITER relevant and future fusion DEMO reactors.
Kawamura, Yoshinori; Arita, Tadaaki; Isobe, Kanetsugu; Shu, Wataru; Yamanishi, Toshihiko
Fusion Engineering and Design, 83(4), p.625 - 633, 2008/05
Times Cited Count：11 Percentile：57.82(Nuclear Science & Technology)Electrochemical hydrogen pump with ceramic proton conductor membrane has been proposed to apply for a blanket tritium recovery system (BTR) of a fusion reactor. SrCe
Yb
O
(SCO) is one of the candidates of membrane. Modification of electrode is one of the methods to enhance the hydrogen transportation capability. In this work, the electrodes of platinum (Pt) and palladium (Pd) were attached to the SCO sample by the sputtering method (sputtering electrode), and its electric conductivity and proton conductivity were measured. Then, they were compared with that of the usual Pt paste electrode. Hydrogen transportation capability was enhanced when the sputtering electrode was applied. Especially, in case of the Pd sputtering electrode, the current density which was about 4 or 5times larger than the usual Pt paste electrode was observed at 0.1% of H
concentration.
Hayashi, Takumi; Isobe, Kanetsugu; Kobayashi, Kazuhiro; Iwai, Yasunori; Kawamura, Yoshinori; Nakamura, Hirofumi; Shu, Wataru; Arita, Tadaaki; Hoshi, Shuichi; Suzuki, Takumi; et al.
Fusion Science and Technology, 52(3), p.651 - 658, 2007/10
Times Cited Count：2 Percentile：18.33(Nuclear Science & Technology)The design studies of Air Detirtiation System have been carried out in JAEA as a contribution of Japan to ITER. For the tritium processing technologies, our efforts have been focused on the R&D of the tritium recovery system of ITER test blanket, using mainly molecular sieve and/or electro-chemical pumping system. A series of fundamental studies on tritium safety technologies, such as tritium behavior in a confinement and its barrier materials, monitoring, accountancy, detritiation and decontamination etc., has been carried out as a major activity in JAEA for ITER and fusion demo reactors. In this paper, the above recent activities on tritium technologies at Tritium Process Lab. in JAEA are summarized for ITER and future fusion reactor.
Arita, Tadaaki*; Yamanishi, Toshihiko; Iwai, Yasunori; Nishi, Masataka; Yamamoto, Ichiro*
Fusion Science and Technology, 41(3), p.1116 - 1120, 2002/05
no abstracts in English
Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; Arita, Tadaaki*; Maruyama, T.*; Kakuta, Toshiya*; Konishi, Satoshi; Enoeda, Mikio; Ohira, Shigeru; Hayashi, Takumi; et al.
Nuclear Fusion, 40(3Y), p.515 - 518, 2000/03
Times Cited Count：6 Percentile：20.77(Physics, Fluids & Plasmas)no abstracts in English
Ohira, Shigeru; Hayashi, Takumi; Nakamura, Hirofumi; Kobayashi, Kazuhiro; Tadokoro, Takahiro*; Nakamura, H.*; Ito, Takeshi*; Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; et al.
Nuclear Fusion, 40(3Y), p.519 - 525, 2000/03
Times Cited Count：24 Percentile：58.20(Physics, Fluids & Plasmas)no abstracts in English
Ohira, Shigeru; Hayashi, Takumi; Nakamura, Hirofumi; Kobayashi, Kazuhiro; Tadokoro, Takahiro*; Nakamura, H.*; Ito, Takeshi*; Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; et al.
Fusion Energy 1998, 3, p.1069 - 1072, 1998/10
no abstracts in English
Arita, Tadaaki; Yamanishi, Toshihiko; Okuno, Kenji; Yamamoto, Ichiro*
Fusion Engineering and Design, 39-40, p.1021 - 1026, 1998/09
Times Cited Count：17 Percentile：77.24(Nuclear Science & Technology)no abstracts in English
Arita, Tadaaki; Yamanishi, Toshihiko; Iwai, Yasunori; Okuno, Kenji; Kobayashi, Noboru*; Yamamoto, Ichiro*
Fusion Technology, 30(3), p.864 - 868, 1996/12
no abstracts in English
Kawamura, Yoshinori; Arita, Tadaaki; Isobe, Kanetsugu; Yamanishi, Toshihiko
no journal, ,
The electrochemical hydrogen pump using the ceramic proton conductor membrane is one of the candidate system that is applied to the blanket tritium recovery system of the fusion reactor. To enhance the hydrogen transportation ability, the electrode material having small particle size is being tried. The author has applied the sputtering as the method of making the electrode having small particle size, and the amount of hydrogen transported via the proton conductor membrane with the sputtering electrode was observed. The amount of hydrogen transported via the membrane with the platinum sputtering electrode became larger than that with the platinum paste electrode, and the advantage of the sputtering electrode was demonstrated.
