Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Takeda, Tetsuaki*; Inagaki, Yoshiyuki; Aihara, Jun; Aoki, Takeshi; Fujiwara, Yusuke; Fukaya, Yuji; Goto, Minoru; Ho, H. Q.; Iigaki, Kazuhiko; Imai, Yoshiyuki; et al.
High Temperature Gas-Cooled Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.5, 464 Pages, 2021/02
As a general overview of the research and development of a High Temperature Gas-cooled Reactor (HTGR) in JAEA, this book describes the achievements by the High Temperature Engineering Test Reactor (HTTR) on the designs, key component technologies such as fuel, reactor internals, high temperature components, etc., and operational experience such as rise-to-power tests, high temperature operation at 950
C, safety demonstration tests, etc. In addition, based on the knowledge of the HTTR, the development of designs and component technologies such as high performance fuel, helium gas turbine and hydrogen production by IS process for commercial HTGRs are described. These results are very useful for the future development of HTGRs. This book is published as one of a series of technical books on fossil fuel and nuclear energy systems by the Power Energy Systems Division of the Japan Society of Mechanical Engineers.
Mineo, Hideaki; Nishihara, Tetsuo; Ohashi, Hirofumi; Goto, Minoru; Sato, Hiroyuki; Takegami, Hiroaki
Nihon Genshiryoku Gakkai-Shi ATOMO
, 62(9), p.504 - 508, 2020/09
High-Temperature Gas-cooled Reactor (HTGR) is one of thermal neutron reactor-type that employs helium gas coolant and graphite moderator. It has excellent inherent safety and can supply high-temperature heat which can be used not only for electric power generation but also for a wide range of application such as hydrogen production. Therefore, HTGR is expected to be an effective technology for reducing greenhouse gases in Japan as well as overseas. In this paper, we will introduce the forefront of technological development that JAEA is working toward the realization of an HTGR system consisting of a high temperature gas reactor and heat utilization facilities such as gas-turbine power generation and hydrogen production.
Mishima, Kaichiro*; Hibiki, Takashi*; Saito, Y.*; Nishihara, Hideaki*; Tobita, Y.*; *; Matsubayashi, Masahito
Nuclear Instruments and Methods in Physics Research A, 424(1), p.229 - 234, 1999/00
Times Cited Count：31 Percentile：88.42(Instruments & Instrumentation)no abstracts in English
Mishima, Kaichiro*; Hibiki, Takashi*; Fujine, Shigenori*; Yoneda, Kenji*; Kanda, Keiji*; Nishihara, Hideaki*; Matsubayashi, Masahito; Tsuruno, Akira
Fifth World Conf. on Neutron Radiography, 0, p.140 - 147, 1996/00
no abstracts in English
Mishima, Kaichiro*; Hibiki, Takashi*; Fujine, Shigenori*; Yoneda, Kenji*; Kanda, Keiji*; Nishihara, Hideaki*; Tsuruno, Akira; Matsubayashi, Masahito; Sobajima, Makoto
Proc. of 2nd Int. Topical Meeting on Neutron Radiography System Design and Characterization, 0, p.309 - 315, 1995/00
no abstracts in English
Hibiki, Takashi*; Mishima, Kaichiro*; Yoneda, Kenji*; Fujine, Shigenori*; Kanda, Keiji*; Nishihara, Hideaki*; Tsuruno, Akira; Matsubayashi, Masahito
Journal of Nuclear Science and Technology, 30(6), p.516 - 523, 1993/06
no abstracts in English
; Shinohara, Yoshikuni; *; *; *; Nishihara, Hideaki*; *; *; Tamura, Seiji*; *
Nihon Genshiryoku Gakkai-Shi, 24(3), p.188 - 198, 1982/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
