Zobrazeno 1 - 10
of 228
pro vyhledávání: '"Tetsuaki TAKEDA"'
Autor:
Kenta FUJIKAMI, Tetsuaki TAKEDA
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 84, Iss 859, Pp 17-00391-17-00391 (2018)
A Very High Temperature Reactor (VHTR) is a next generation nuclear reactor system. From a view point of safety characteristic, a passive cooling system should be designed for the VHTR as a best way of a reactor vessel cooling system (VCS). Therefore
Externí odkaz:
https://doaj.org/article/957644990485433ab46d10ed1b62419b
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 5, Pp 534-545 (2015)
In the very high temperature reactor (VHTR), which is a next generation nuclear reactor system, ceramics are used as a fuel coating material and graphite is used as a core structural material. Even if a depressurization accident occurs and the reacto
Externí odkaz:
https://doaj.org/article/c76c319053a948d68fcb555818a5b57e
Autor:
Nanami Kobayashi, Tetsuaki Takeda
Publikováno v:
The Proceedings of the International Conference on Power Engineering (ICOPE). :2021-0281
Hot water supply performance of a ground source heat pump that use open-type direct expansion method
Publikováno v:
The Proceedings of the International Conference on Power Engineering (ICOPE). :2021-0201
Autor:
Dai MORIYA, and Tetsuaki TAKEDA
Publikováno v:
The Proceedings of the International Conference on Power Engineering (ICOPE). :2021-0181
Autor:
Yasuaki Takayama, Tetsuaki Takeda
Publikováno v:
Volume 4: Student Paper Competition.
A very high-temperature reactor (VHTR) is a next-generation nuclear reactor systems. A gas cooling system with natural circulation is considered as a candidate for the pressure vessel cooling system (VCS) of the VHTR. The Japan Atomic Energy Agency i
Autor:
Takeaki Ube, Tetsuaki Takeda
Publikováno v:
Volume 4: Student Paper Competition.
A depressurization accident involving the rupture of the primary cooling pipe of the Gas Turbine High Temperature Reactor 300 cogeneration (GTHTR300C), which is a very-high-temperature reactor, is a design-based accident. When the primary pipe connec
Autor:
Gota Suga, Tetsuaki Takeda
A Very High Temperature Reactor (VHTR) is one of the next generation nuclear systems. From a view point of safety characteristics, a passive cooling system should be designed as the best way of a reactor vessel cooling system (VCS) in the VHTR. There
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9965e1c5f9625cc56dcc6519f0bf53c8
https://doi.org/10.1115/1.0000500v
https://doi.org/10.1115/1.0000500v
Autor:
Jun Aihara, Yukio Tachibana, Shoji Takada, Yoshiyuki Inagaki, Tetsuo Nishihara, Shohei Ueta, Junya Sumita, Minoru Goto, Tetsuaki Takeda, Taiju Shibata, Nariaki Sakaba, Kazuhiko Kunitomi, Tatsuo Iyoku
The following RD fuel, core components and reactor internals, passive cooling system, intermediate heat exchanger, and basic feature of air ingress during primary pipe rupture accident. As for the fuel, the design criteria and specifications for the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::469a8b0e21dab73f5e374428b75d033b
https://doi.org/10.1016/b978-0-12-821031-4.00003-8
https://doi.org/10.1016/b978-0-12-821031-4.00003-8
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