Zobrazeno 1 - 10
of 237
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7a053850b613d13386828c40389b1fbf
https://doi.org/10.1299/jsmeicope.2021.15.2021-0281
https://doi.org/10.1299/jsmeicope.2021.15.2021-0281
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c5fe749fa225a92067ddeb55391cd378
https://doi.org/10.1299/jsmeicope.2021.15.2021-0201
https://doi.org/10.1299/jsmeicope.2021.15.2021-0201
Autor:
Dai MORIYA, and Tetsuaki TAKEDA
Publikováno v:
The Proceedings of the International Conference on Power Engineering (ICOPE). :2021-0181
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7ff3174523d516912ba0f79493b72e08
https://doi.org/10.1299/jsmeicope.2021.15.2021-0181
https://doi.org/10.1299/jsmeicope.2021.15.2021-0181
Autor:
Tetsuaki Takeda, Yoshiyuki Inagaki
High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::51c9cafdfa15e1df74a2400d2032be37
https://doi.org/10.1115/icone28-64552
https://doi.org/10.1115/icone28-64552
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8dba05f565e06aff61f61a065cdb1528
https://doi.org/10.1115/icone28-64553
https://doi.org/10.1115/icone28-64553
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