Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Yasunobu Nomoto"'
Autor:
Masato Ono, Hiroyuki Inoi, Yasunobu Nomoto, Masayuki Shinozaki, Kazumi Tokuhara, Hirofumi Ohashi, Shimpei Hamamoto, Yosuke Shimazaki, Atsushi Shimizu, Kazuhiko Iigaki
Publikováno v:
Nuclear Engineering and Design. 386:111585
In the late 1980s, the seismic classification of the high temperature engineering test reactor (HTTR) was formulated during its design stage. Because of the HTTR’s lack of operation experiences to sufficiently understand the safety characteristics
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
Autor:
Minoru Goto, Yoshitomo Inaba, Hirofumi Ohashi, Hiroki Noguchi, Yasunobu Nomoto, Yoshiyuki Imai, Yuji Fukaya, Yukio Tachibana, Junya Sumita, Xing Yan, Hiroyuki Sato, Yujiro Tazawa, Jun Aihara
Publikováno v:
International Journal of Nuclear Energy. 2013:1-18
Japan Atomic Energy Agency has conducted a conceptual design of a 50 MWt small-sized high temperature gas cooled reactor (HTGR) for multiple heat applications, named HTR50S, with the reactor outlet coolant temperature of 750°C and 900°C. It is firs
Publikováno v:
Progress in Nuclear Energy. 50:325-332
Power generation systems such as steam turbine cycle, helium turbine cycle and supercritical CO2 (S-CO2) turbine cycle are examined for the prototype nuclear fusion reactor. Their achievable cycle thermal efficiencies are revealed to be 40%, 34% and