Zobrazeno 1 - 10
of 53
pro vyhledávání: '"Junya Sumita"'
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:
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:
Tetsuo Nishihara, Minoru Goto, Takeshi Aoki, Taiju Shibata, Yukio Tachibana, Tatsuo Iyoku, Yoshitomo Inaba, Shinji Kubo, Tetsuaki Takeda, Hiroaki Takegami, Shoji Takada, Junya Sumita, Jun Aihara, Shohei Ueta, Koei Sasaki, Nobuyuki Tanaka, Naoki Mizuta, Odtsetseg Myagmarjav, Hirofumi Ohashi, Kazuhiko Kunitomi, Xing Yan, Hiroyuki Sato, Nariaki Sakaba, Hiroki Noguchi, Yoshiyuki Inagaki, Seiji Kasahara, Yoshiyuki Imai, Yuji Fukaya, Yu Kamiji
High temperature gas-cooled reactor (HTGR) can be used in various ways such as hydrogen production and process heat supply as well as power generation. For the commercial HTGR, R&D on the system, and safety designs, key components for heat applicatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c044af71c341376e36eb2771f075a3b6
https://doi.org/10.1016/b978-0-12-821031-4.00005-1
https://doi.org/10.1016/b978-0-12-821031-4.00005-1
Autor:
Takashi Osaki, A.A. Shaimerdenov, Ulzhan Koztayeva, Nariaki Sakaba, Natalya Romanova, Hideki Kato, Shoichi Izawa, Naoki Mizuta, Shamil Gizatulin, Junya Sumita, Taiju Shibata, Daulet Dyussambayev, Takenori Muto
Publikováno v:
2020 7th International Congress on Energy Fluxes and Radiation Effects (EFRE).
Oxidation-induced damage in nuclear reactor materials is one of the important safety issues in accidents. In particular, graphite materials are used for the internal components of a high temperature gas-cooled reactor (HTGR) due to its excellent neut
Autor:
Hiroyuki Sato, Shoichi Horii, Satoru Yamada, Atsuhiko Terada, Seiji Kasahara, Xing L. Yan, Yasunobu Nomoto, Junya Sumita, Jin Iwatsuki, Kazumasa Suyama, Koichi Suzuki, M. Oono, Yukio Tachibana, Yoshiyuki Imai
Publikováno v:
Nuclear Engineering and Design. 329:223-233
The pre-licensing design of an HTGR cogeneration test plant to be coupled to JAEA’s existing test reactor HTTR is discussed. The plant is designed to demonstrate the system of JAEA commercial plant design of Gas Turbine High Temperature Reactor for
Publikováno v:
Nuclear Engineering and Design. 329:247-254
This paper presents the system performance evaluation for HTTR gas turbine cogeneration test plant (HTTR-GT/H2 plant) so as to confirm that the design meets the requirements with respect to the demonstration test objective. Start-up and shut down ope
Publikováno v:
Key Engineering Materials. 697:797-806
Nuclear energy is one of the most promising energy sources to satisfy energy security, environmental protection, and efficient supply. The High Temperature Gas-cooled Reactor (HTGR) has attractive inherent safety features and it can be used as many k
Publikováno v:
Journal of Nuclear Science and Technology. 51:1364-1372
Graphite material is used for internal structures in high temperature gas-cooled reactor. The core components and graphite core support structures are so designed as to maintain the structural inte...
Autor:
Masatoshi Kuroda, Taiju Shibata, Teruaki Yamada, Kazuhiro Sawa, Yuki Matsushima, Junya Sumita, Ichiro Fujita
Publikováno v:
Nuclear Engineering and Design. 271:323-326
In order to investigate the effects of the experimental methodology and the notch angle on the fracture toughness of the fine-grained isotropic nuclear graphites IG-110 and IG-430, the three-point-bending test, which has been recently proposed as the