Zobrazeno 1 - 10
of 76
pro vyhledávání: '"Shigeaki Nakagawa"'
Publikováno v:
Mechanical Engineering Journal, Vol 4, Iss 3, Pp 16-00495-16-00495 (2016)
One important safety design consideration for high temperature gas-cooled reactor (HTGR) is air ingress following a rupture of the reactor pressure boundary such as primary piping. The air intrusion to the reactor core held at high temperature throug
Externí odkaz:
https://doaj.org/article/e63370a532c14be5b0301ac48f908ad4
Autor:
Shigeaki Nakagawa, Hideaki Matsuura, Kenji Tobita, Minoru Goto, Teppei Otsuka, Yuki Koga, Takuro Suganuma, Ryo Okamoto, Etsuo Ishitsuka, Kazunari Katayama
Publikováno v:
Fusion Engineering and Design. 146:1077-1081
Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption sp
Publikováno v:
Annals of Nuclear Energy. 168:108911
Autor:
Minoru Goto, Shigeaki Nakagawa, Hideaki Matsuura, Hiroyuki Nakaya, Kazunari Katayama, Yoshitomo Inaba, Keisuke Okumura
Publikováno v:
Fusion Engineering and Design. 136:357-361
A high-temperature, gas-cooled reactor (HTGR) is proposed as a tritium production device that has the potential to produce a large amount of tritium using the 6Li(n,α)T reaction without major changes to the original reactor core design. In an HTGR d
Autor:
Satoru Nagasumi, Ryo Okamoto, Etsuo Ishitsuka, Kazunari Katayama, Yosuke Shimazaki, Teppei Otsuka, Yuma Ida, Shigeaki Nakagawa, Yuki Koga, Minoru Goto, Hideaki Matsuura
Publikováno v:
Fusion Engineering and Design. 136:587-591
Large quantities of tritium are required to start up fusion reactors and conducts engineering tests using tritium for a fusion blanket system. However, tritium is very rare and kg orders of tritium must be produced artificially. Tritium production, b
Autor:
Jun Aihara, Takeshi Aoki, Yusuke Fujiwara, Yuji Fukaya, Minoru Goto, Hai Quan Ho, Kazuhiko Iigaki, Yoshiyuki Imai, Yoshitomo Inaba, Yoshiyuki Inagaki, Hiroyuki Inoi, Etsuo Ishitsuka, Jin Iwatsuki, Tatsuo Iyoku, Yu Kamiji, Seiji Kasahara, Taiki Kawamoto, Makoto Kondo, Shinji Kubo, Kazuhiko Kunitomi, Hideaki Mineo, Naoki Mizuta, Keisuke Morita, Odtsetseg Myagmarjav, Satoru Nagasumi, Shigeaki Nakagawa, Tetsuo Nishihara, Hiroki Noguchi, Naoki Nojiri, Hirofumi Ohashi, Masato Ono, Akio Saikusa, Nariaki Sakaba, Koei Sasaki, Hiroyuki Sato, Hiroaki Sawahata, Taiju Shibata, Yosuke Shimazaki, Atsushi Shimizu, Masayuki Shinozaki, Junya Sumita, Yukio Tachibana, Shoji Takada, Kuniyoshi Takamatsu, Tetsuaki Takeda, Hiroaki Takegami, Nobuyuki Tanaka, Daisuke Tochio, Takahiro Uesaka, Shohei Ueta, Xing Yan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::117973978957c77aaf7ef0443f2a5dcb
https://doi.org/10.1016/b978-0-12-821031-4.00011-7
https://doi.org/10.1016/b978-0-12-821031-4.00011-7
Autor:
Minoru Goto, Kazuhiko Kunitomi, Taiju Shibata, Masato Ono, Tatsuo Iyoku, Yusuke Fujiwara, Akio Saikusa, Taiki Kawamoto, Masayuki Shinozaki, Kazuhiko Iigaki, Satoru Nagasumi, Hai Quan Ho, Yosuke Shimazaki, Atsushi Shimizu, Takahiro Uesaka, Nariaki Sakaba, Naoki Nojiri, Junya Sumita, Shoji Takada, Makoto Kondo, Shigeaki Nakagawa, Keisuke Morita, Tetsuo Nishihara, Shohei Ueta, Yukio Tachibana, Daisuke Tochio
The following design details of the high temperature engineering test reactor (HTTR) are described: nuclear, thermal-hydraulic seismic and safety performance, metal and graphite components, core components and reactor internals, and cooling, reactivi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c68055eacd8d52967c6e74bb1e60cfab
https://doi.org/10.1016/b978-0-12-821031-4.00002-6
https://doi.org/10.1016/b978-0-12-821031-4.00002-6
Autor:
Minoru Goto, Taiju Shibata, Masayuki Shinozaki, Shoji Takada, Tatsuo Iyoku, Yukio Tachibana, Yuji Fukaya, Nariaki Sakaba, Shigeaki Nakagawa, Etsuo Ishitsuka, Kuniyoshi Takamatsu, Hiroyuki Inoi, Kazuhiko Kunitomi, Tetsuo Nishihara, Akio Saikusa, Hai Quan Ho, Hiroaki Sawahata, Daisuke Tochio
The first criticality of the high temperature engineering test reactor (HTTR) was achieved on November 10, 1998. After improvement of the reactor system and performance confirmation, the rise-to-power test was started in September 1999. The HTTR achi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ad004bf35e376e167ccd4d34e8bdc7b
https://doi.org/10.1016/b978-0-12-821031-4.00004-x
https://doi.org/10.1016/b978-0-12-821031-4.00004-x
Autor:
Yuki Koga, Etsuo Ishitsuka, Minoru Goto, Yoshiteru Sakamoto, Shimpei Hamamoto, Kenji Tobita, Shigeaki Nakagawa, Kazunari Katayama, Ryoji Hiwatari, Teppei Otsuka, Hideaki Matsuura, Satoshi Konishi, Youji Someya
Publikováno v:
Nuclear Engineering and Design. 386:111584
Tritium is required for research and development activities for the deuterium–tritium (DT) fusion reactor and fueling the DEMOnstration Power Station (DEMO). However, tritium is a very rare nuclide and must be produced artificially. Tritium product
Autor:
Shigeaki Nakagawa, Etsuo Ishitsuka, Hideaki Matsuura, Yuki Koga, Shinpei Hamamoto, Kenji Tobita, Satoshi Konishi, Kazunari Katayama, Motomasa Naoi, Ryoji Hiwatari, Takuro Suganuma, Teppei Otsuka, Youji Someya, Minoru Goto, Yoshiteru Sakamoto
Publikováno v:
Fusion Engineering and Design. 169:112441
The production of tritium (T) using high-temperature gas-cooled reactors (HTGRs) has been studied for a prior engineering research with T handling and initial T possession in demonstration fusion reactors. Stable containment of T in Li-loading rods d