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Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.952 - 954, 2004/11
Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.
Enoeda, Mikio; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Miki, Nobuharu*; Homma, Takashi; Akiba, Masato; Konishi, Satoshi; Nakamura, Hirofumi; Kawamura, Yoshinori; et al.
Nuclear Fusion, 43(12), p.1837 - 1844, 2003/12
Times Cited Count：101 Percentile：93.45(Physics, Fluids & Plasmas)no abstracts in English
Yamada, Hirokazu*; Nagao, Yoshiharu; Kawamura, Hiroshi; Nakao, Makoto*; Uchida, Munenori*; Ito, Haruhiko
Fusion Engineering and Design, 69(1-4), p.269 - 273, 2003/09
Times Cited Count：14 Percentile：66.94(Nuclear Science & Technology)no abstracts in English
Yanagi, Yoshihiko*; Sato, Satoshi; Enoeda, Mikio; Hatano, Toshihisa; Kikuchi, Shigeto*; Kuroda, Toshimasa*; Kosaku, Yasuo; Ohara, Yoshihiro
Journal of Nuclear Science and Technology, 38(11), p.1014 - 1018, 2001/11
Times Cited Count：24 Percentile：83.28(Nuclear Science & Technology)no abstracts in English
Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; Nakahira, Masataka; *; Hashimoto, T.*; Kuroda, Toshimasa*; Takatsu, Hideyuki
JAERI-Tech 95-021, 25 Pages, 1995/03
no abstracts in English
*; *; Seki, Yasushi
JAERI-M 91-058, 48 Pages, 1991/03
no abstracts in English
;
JAERI-M 8896, 11 Pages, 1980/06
no abstracts in English
*; ;
JAERI-M 8739, 36 Pages, 1980/03
no abstracts in English
*;
JAERI-M 7915, 70 Pages, 1978/10
no abstracts in English
*; ;
JAERI-M 6475, 18 Pages, 1976/03
no abstracts in English
; ; *
JAERI-M 6460, 21 Pages, 1976/03
no abstracts in English
*;
JAERI-M 5855, 31 Pages, 1974/09
no abstracts in English
Kawamura, Yoshinori
no journal, ,
The most important subject in the ITER-TBM test program is the estimation of TBR based on the information of neutron entered into TBM and of tritium recovered from TBM, and is the showing good prospect of TBR for DEMO. To discuss TBR estimation method in TBM test program, JAEA is carrying out the tritium generation and recovery experiments using simulated blanket at Fusion Neutron Source facility (FNS). At FNS, more accurate TBR estimation is possible by the comparison among the amount of calculated tritium generation, observed tritium generation, and tritium recovery. In the case of TBM, the neutron estimation is not so easy, because neutron source is a heterogeneous plasma having volume, and the plasma is generated in the form of pulses. So, TBR estimation in TBM program will need more effort.
