High temperature gas-cooled reactors
Takeda, Tetsuaki*; Inagaki, Yoshiyuki; Aihara, Jun ; Aoki, Takeshi ; Fujiwara, Yusuke ; Fukaya, Yuji ; Goto, Minoru ; Ho, H. Q. ; Iigaki, Kazuhiko ; Imai, Yoshiyuki ; Inaba, Yoshitomo ; Inoi, Hiroyuki; Ishitsuka, Etsuo ; Iwatsuki, Jin ; Iyoku, Tatsuo; Kamiji, Yu; Kasahara, Seiji ; Kawamoto, Taiki; Kondo, Makoto; Kubo, Shinji ; Kunitomi, Kazuhiko ; Mineo, Hideaki ; Mizuta, Naoki ; Morita, Keisuke; Myagmarjav, O. ; Nagasumi, Satoru; Nakagawa, Shigeaki ; Nishihara, Tetsuo ; Noguchi, Hiroki ; Nojiri, Naoki ; Ohashi, Hirofumi ; Ono, Masato ; Saikusa, Akio ; Sakaba, Nariaki ; Sasaki, Koei ; Sato, Hiroyuki ; Sawahata, Hiroaki ; Shibata, Taiju ; Shimazaki, Yosuke ; Shimizu, Atsushi ; Shinozaki, Masayuki; Sumita, Junya ; Tachibana, Yukio ; Takada, Shoji; Takamatsu, Kuniyoshi ; Takegami, Hiroaki ; Tanaka, Nobuyuki ; Tochio, Daisuke ; Uesaka, Takahiro; Ueta, Shohei ; Yan, X.
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 950C, 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.