Conceptual design of the blanket tritium recovery system for the prototype fusion reactor

Kakuta, Toshiya*; Hirata, Shingo*; Mori, Seiji*; Konishi, Satoshi; Kawamura, Yoshinori; Nishi, Masataka; Ohara, Yoshihiro

Fusion Science and Technology, 41(3), p.1069 - 1073, 2002/05

Research-and-development of the supercritical water-cooled prototype fusion reactor which has cost competitiveness has been performed in Japan Atomic Energy Research Institute (JAERI). It is necessary to establish immediately the design concept of the blanket tritium recovery system which collects tritium continuously and safely from the supercritical water-cooled blanket because fuel self-sufficiency is inevitable in the prototype reactor. The candidate systems are; 1) batch-processing cryogenic molecular sheave bed recovery system with cryogenic temperature operation, 2) continuous processing Pd membrane penetration recovery system with high vacuum operation. In the present study, however, the third candidate system, the hydrogen pump system with protonic conductors, was investigated. As a result of the study, it was made clear that the system with minimized energy consumption and minimized accidental tritium release could be realized by using the hydrogen pump for the blanket tritium recovery system of the prototype fusion reactor.

Tritium permeation behavior implanted into pure tungsten and its isotope effect

Nakamura, Hirofumi; Hayashi, Takumi; Kakuta, Toshiya*; Suzuki, Takumi; Nishi, Masataka

Journal of Nuclear Materials, 297(3), p.285 - 291, 2001/09

https://doi.org/10.1016/S0022-3115(01)00635-3

The isotope effect on the implantation-driven permeation of pure tritium (T) and deuterium (D) through nickel was investigated, respectively. The rate-determining processes of backward flow at the upstream surface and permeation at the down-stream surface were found to be as follows: recombination on up-stream surface and diffusion at down-stream side in a lower temperature region, whereas recombination on both surfaces in a higher temperature region for T and D, respectively. The diffusion coefficients of T and D derived by analyzing the obtained transient data of permeation in the lower temperature region were in good agreement with literature data of deuterium. The obtained activation energy of diffusion for T and D suggested the tendency of mass dependence. The surface recombination coefficients for both isotopes were also derived and showed in good agreement with literature data. As a result, the experimental results indicated the surface recombination could be attributed to the isotope effect of the permeation between T and D rather than the diffusion.

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

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

https://doi.org/10.1088/0029-5515/40/3Y/311

no abstracts in English

Demonstration of the integrated fusion fuel loop at the tritium process laboratory of the Japan Atomic Energy Research Institute

Yamanishi, Toshihiko; Konishi, Satoshi; Hayashi, Takumi; Kawamura, Yoshinori; Iwai, Yasunori; Maruyama, T.*; Kakuta, Toshiya*; Ohira, Shigeru; Nakamura, Hirofumi; Kobayashi, Kazuhiro; et al.

Fusion Technology, 34(3), p.536 - 540, 1998/11

no abstracts in English

Experimental and analytical study on membrane detritiation process

Hirata, Shingo*; Kakuta, Toshiya*; Ito, H.*; Suzuki, T.*; Hayashi, Takumi; Ishida, Toshikatsu*; Matsuda, Yuji; Okuno, Kenji

Fusion Technology, 28(3), p.1521 - 1526, 1995/10

no abstracts in English

Demonstration of incinerating and melting system by high frequency induction furnace, 1; Demonstration of incinerating and melting system

Kakuta, Toshiya*; Kuchiki, Norikazu*; Sato, Yasushi*; Matsumoto, Takeshi; Donomae, Yasushi

no journal, , 

JP, 2007-218796   Patent publication (In Japanese)

no abstracts in English