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Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 53(11), p.1758 - 1765, 2016/11
Times Cited Count：10 Percentile：65.38(Nuclear Science & Technology)Shibamoto, Yasuteru; Kukita, Yutaka*; Nakamura, Hideo
Proceedings of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11) (CD-ROM), 15 Pages, 2005/10
no abstracts in English
Takamatsu, Kuniyoshi; Nakagawa, Shigeaki
JAERI-Tech 2005-030, 21 Pages, 2005/05
JAERI-Tech-2005-030.pdf:1.06MB
The High Temperature engineering Test Reactor (HTTR) is a graphite moderated and gas cooled reactor with the thermal power of 30MW and the reactor outlet coolant temperature of 850
C/950C. Rise-to-power test in the HTTR was performed from March 31th to May 1st in 2004 as phase 5 test up to 30MW in the high temperature test operation mode. It was confirmed that the thermal reactor power and the reactor outlet coolant temperature reached to 30MW and 950C respectively on April 19th. Achievement of the reactor outlet coolant temperature of 950C is the first time in Japan as well as the world. This report describes proposal for evaluation methods of reactor outlet coolant temperature in the HTGRs through the HTTR operation experiments. The equation is derived from relationships among PRM reading values, reactor outlet coolant temperature, reactor thermal power and heat removal by VCS. The deliberation processes in this study will be applicable to the research and developments of HTGRs in the future.
Ashikagaya, Yoshinobu; Kawasaki, Tomokatsu; Yoshino, Toshiaki; Ishida, Keiichi
JAERI-Tech 2005-010, 81 Pages, 2005/03
JAERI-Tech-2005-010.pdf:16.65MB
no abstracts in English
C for the first time in the worldKawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo
Nihon Genshiryoku Gakkai-Shi, 46(5), P. 301, 2004/05
no abstracts in English
Saito, Kenji; Nakagawa, Shigeaki; Hirato, Yoji; Kondo, Makoto; Sawahata, Hiroaki; Tsuchiyama, Masaru*; Ando, Toshio*; Motegi, Toshihiro; Mizushima, Toshihiko; Nakazawa, Toshio
JAERI-Tech 2004-042, 26 Pages, 2004/04
JAERI-Tech-2004-042.pdf:1.16MB
The reactor control system of HTTR is composed of the reactor power control system, the reactor inlet coolant temperature control system, the primary coolant flow rate control system and so on. The reactor control system of HTTR achieves reactor power 30MW, reactor outlet coolant temperature 850C, reactor inlet coolant temperature 395C under the condition that primary coolant flow rate is fixed. In the Rise-to-Power Test, the performance test of the reactor inlet coolant temperature control system was carried out in order to confirm the control capability of this control system. This report shows the test results of performance test. As a result, the control parameters, which can control the reactor inlet coolant temperature stably during the reactor operation, were successfully selected. And it was confirmed that the reactor inlet coolant temperature control system has the capability of controlling the reactor inlet coolant temperature stably against any disturbances on the basis of operational condition of HTTR.
Nakamura, Jinichi; Sugiyama, Tomoyuki; Nakamura, Takehiko; Kanazawa, Toru; Sasajima, Hideo
JAERI-Tech 2003-008, 32 Pages, 2003/03
JAERI-Tech-2003-008.pdf:1.49MB
no abstracts in English
Hayashi, Takafumi*; Suyama, Kenya; Mochizuki, Hiroki*; Nomura, Yasushi
JAERI-Tech 2001-041, 158 Pages, 2001/06
JAERI-Tech-2001-041.pdf:5.15MB
no abstracts in English
; Onuki, Akira; Murao, Yoshio
Validation of Systems Transients Analysis Codes (FED-Vol. 223), 0, 8 Pages, 1995/00
no abstracts in English
Maruyama, So; Fujimoto, Nozomu; Sudo, Yukio; Murakami, Tomoyuki*; Fujii, Sadao*
Nucl. Eng. Des., 152, p.183 - 196, 1994/00
Times Cited Count：16 Percentile：78.21(Nuclear Science & Technology)no abstracts in English
Tanzawa, Sadamitsu; ;
Journal of Nuclear Science and Technology, 30(4), p.281 - 290, 1993/04
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
Maruyama, So; Yamashita, Kiyonobu; Fujimoto, Nozomu; Murata, Isao; Shindo, Ryuichi; Sudo, Yukio
The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.304 - 311, 1990/09
no abstracts in English
Fujimoto, Nozomu; Maruyama, So; Sudo, Yukio
JAERI-M 89-049, 53 Pages, 1989/05
no abstracts in English
; ; Tasaka, Kanji
Journal of Nuclear Science and Technology, 25(2), p.169 - 179, 1988/02
no abstracts in English
Suzuki, Kunihiro
JAERI-M 87-160, 75 Pages, 1987/10
no abstracts in English
JAERI-M 85-196, 52 Pages, 1985/12
no abstracts in English
JAERI-M 84-172, 290 Pages, 1984/09
no abstracts in English
Suzuki, Katsuo;
JAERI-M 83-191, 22 Pages, 1983/11
no abstracts in English
;
JAERI-M 83-068, 18 Pages, 1983/04
no abstracts in English
; ;
JAERI-M 82-101, 43 Pages, 1982/08
no abstracts in English
