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Isogawa, Hiroki*; Naoi, Motomasa*; Yamasaki, Seiji*; Ho, H. Q.; Katayama, Kazunari*; Matsuura, Hideaki*; Fujimoto, Nozomu*; Ishitsuka, Etsuo
JAEA-Technology 2022-015, 18 Pages, 2022/07
JAEA-Technology-2022-015.pdf:1.37MB
As a summer holiday practical training 2021, the impact of 10 years long-term shutdown on critical control rod position of the HTTR and the delayed neutron fraction (
) of the VHTRC-1 core were investigated using Monte-Carlo MVP code. As a result, a long-term shutdown of 10 years caused the critical control rods of the HTTR to withdraw about 4.0
0.8 cm compared to 3.9 cm in the experiment. The change in critical control rods position of the HTTR is due to the change of some fission products such as 
Pu, Am, 
Pm, Sm, 
Gd. Regarding the calculation of the VHTRC-1 core, the value is underestimate of about 10% in comparison with the experiment value.
Takamatsu, Kuniyoshi; Matsumoto, Tatsuya*; Morita, Koji*
Annals of Nuclear Energy, 96, p.137 - 147, 2016/10
Times Cited Count：5 Percentile：43.12(Nuclear Science & Technology)After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. Specifically, emergency power generators are not necessary and the decay heat can be passively removed for a long time, even forever if the heat removal capacity of the RCCS is sufficient. We can also define the experimental conditions on radiation and natural convection for the scale-down heat removal test facility.
Takamatsu, Kuniyoshi; Matsumoto, Tatsuya*; Morita, Koji*
Proceedings of 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016) (CD-ROM), p.1250 - 1257, 2016/04
After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. Specifically, emergency power generators are not necessary and the decay heat can be passively removed for a long time, even forever if the heat removal capacity of the RCCS is sufficient. We can also define the experimental conditions on radiation and natural convection for the scale-down heat removal test facility.
Takamatsu, Kuniyoshi; Hu, R.*
Annals of Nuclear Energy, 77, p.165 - 171, 2015/03
Times Cited Count：14 Percentile：72.94(Nuclear Science & Technology)A new, highly efficient reactor cavity cooling system (RCCS) with passive safety features without a requirement for electricity and mechanical drive is proposed. The RCCS design consists of continuous closed regions; one is an ex-reactor pressure vessel (RPV) region and another is a cooling region having heat transfer area to ambient air assumed at 40 (
C). The RCCS uses a novel shape to efficiently remove the heat released from the RPV with radiation and natural convection. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal.
Takamatsu, Kuniyoshi; Nakagawa, Shigeaki
Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(1), p.45 - 56, 2006/03
The HTTR (High Temperature Engineering Test Reactor), which has thermal output of 30MW, coolant inlet temperature of 395C and coolant outlet temperature of 850C/950C, is a first high temperature gas-cooled reactor (HTGR) in Japan. The HTGR has a high inherent safety potential to accident condition. Safety demonstration tests using the HTTR are underway in order to demonstrate such excellent inherent safety features of the HTGR. A one-point core dynamics approximation with one fuel channel model had applied to this analysis. It was found that the analytical model for core dynamics couldn't simulate the reactor power behavior accurately. This report proposes an original method using temperature coefficients of some regions in the core. It is crucial to evaluate this method precisely to simulate a performance of HTGR during the test.
Hanawa, Satoshi; Sumita, Junya; Shibata, Taiju; Ishihara, Masahiro; Iyoku, Tatsuo; Sawa, Kazuhiro
Transactions of 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT-18), p.600 - 605, 2005/08
no abstracts in English
Yamashita, Kiyonobu; Ando, Hiroei; Nojiri, Naoki; Fujimoto, Nozomu; Nakata, Tetsuo*; Watanabe, Takashi*; Yamane, Tsuyoshi; Nakano, Masaaki*
Proc. of SARATOGA 1997, 2, p.1557 - 1566, 1997/00
no abstracts in English
Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; Fujimoto, Nozomu; Takeda, Takeshi
Nuclear Science and Engineering, 122, p.212 - 228, 1996/00
Times Cited Count：23 Percentile：85.69(Nuclear Science & Technology)no abstracts in English
Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko; Fujisaki, Shingo
PHYSOR 96: Int. Conf. on the Physics of Reactors, 2, p.E281 - E289, 1996/00
no abstracts in English
/
of VHTRC-4 coreYamane, Tsuyoshi; Akino, Fujiyoshi;
PHYSOR 96: Int. Conf. on the Physics of Reactors, 2, p.E290 - E299, 1996/00
no abstracts in English
; Akino, Fujiyoshi; Yamane, Tsuyoshi; ; Kitadate, Kenji; ; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko
JAERI 1305, 138 Pages, 1987/08
no abstracts in English
Nuclear Science and Engineering, 97, p.145 - 160, 1987/00
Times Cited Count：2 Percentile：29.75(Nuclear Science & Technology)no abstracts in English
; ; ;
JAERI-M 85-187, 98 Pages, 1985/11
no abstracts in English
; ; *; ;
JAERI-M 85-184, 105 Pages, 1985/11
no abstracts in English
; ; *; ; ; ; ; *
JAERI-M 85-183, 129 Pages, 1985/11
no abstracts in English
; ; ; *; *
JAERI-M 85-048, 70 Pages, 1985/04
no abstracts in English
; ; ;
Nihon Genshiryoku Gakkai-Shi, 27(12), p.1133 - 1135, 1985/00
Times Cited Count：1 Percentile：24.15(Nuclear Science & Technology)no abstracts in English
Suzuki, Katsuo;
JAERI-M 83-191, 22 Pages, 1983/11
no abstracts in English
; ; ; ; ; ; ; ; Suzuki, Katsuo;
JAERI-M 82-103, 137 Pages, 1982/09
no abstracts in English
; ; ; ; ; ; ; ; ; Suzuki, Katsuo; et al.
JAERI-M 82-102, 368 Pages, 1982/09
no abstracts in English
