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JAEA Reports

Journal Articles

ROSA-AP600 Experiment simulating a steam generator tube rupture transient

Nakamura, Hideo; Kukita, Yutaka; L.S.Ghan*; R.R.Schultz*

Proc. of 1997 Int. Meeting on Advanced Reactors Safety, 0, p.1245 - 1252, 1997/06

no abstracts in English

Journal Articles

Evaluation on driving force of natural circulation in downcomer for passive residual heat removal system in JAERI passive safety reactor JPSR

Kunii, Katsuhiko; Iwamura, Takamichi; Murao, Yoshio

Journal of Nuclear Science and Technology, 34(1), p.21 - 29, 1997/01

 Times Cited Count:1 Percentile:14.48(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of PSA methodology to design improvement of JAERI passive safety reactor (JPSR)

Iwamura, Takamichi; Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.316 - 326, 1996/04

 Times Cited Count:1 Percentile:14.33(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Safety analyses of a passive safety light water reactor JPSR

Araya, Fumimasa; Iwamura, Takamichi; Yoshida, Hiroyuki; Kunii, Katsuhiko; Okumura, Keisuke; Murao, Yoshio

10th Pacific Basin Nuclear Conf. (10-PBNC), 1, p.299 - 305, 1996/00

no abstracts in English

Journal Articles

Passive heat removal by vessel cooling system of HTTR during no forced cooling accidents

Kunitomi, Kazuhiko; Nakagawa, Shigeaki; Shinozaki, Masayuki

Nucl. Eng. Des., 166(2), p.179 - 190, 1996/00

 Times Cited Count:22 Percentile:84.55(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis for thermal fluid dynamics in downcomer of JAERI passive safety reactor (JPSR)

Kunii, Katsuhiko; Iwamura, Takamichi; Murao, Yoshio

Proceedings of 3rd JSME/ASME Joint International Conference on Nuclear Engineering, Vol.2, p.1017 - 1022, 1995/00

no abstracts in English

Journal Articles

Thermal fluid flow analysis in downcomer of JAERI passive safety light water reactor (JPSR)

Kunii, Katsuhiko; Iwamura, Takamichi; Murao, Yoshio

Prog. Nucl. Energy, 29(SUPPL), p.405 - 412, 1995/00

no abstracts in English

Oral presentation

Investigation on heat transfer characteristics of reactor cavity cooling system for HTGR

Hosomi, Seisuke*; Yamaguchi, Shuhei*; Akashi, Tomoyasu*; Matsumoto, Tatsuya*; Liu, W.*; Morita, Koji*; Takamatsu, Kuniyoshi

no journal, , 

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. After building the scale-down heat removal test facility, we conducted experiments and analyses to understand the heat-transfer characteristics. As a result, we could assess effect of radiation and natural convection quantitatively for passive decay heat removal from the RPV.

Oral presentation

An Experimental investigation on heat transfer characteristics using a scaled model of a reactor cavity cooling system with passive safety features

Yamaguchi, Shuhei*; Sato, Noriyasu*; Matsumoto, Tatsuya*; Morita, Koji*; Takamatsu, Kuniyoshi

no journal, , 

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. Last year, we built the scale-down heat removal test facility and now conduct experiments to understand the heat-transfer characteristics. As a result, we could assess effect of radiation quantitatively for passive decay heat removal from the RPV.

Oral presentation

New Reactor Cavity Cooling System (RCCS) having passive safety features, 2; Experimental study on heat transfer characteristics using a scale model

Sato, Noriyasu*; Yamaguchi, Shuhei*; Matsumoto, Tatsuya*; Morita, Koji*; Takamatsu, Kuniyoshi

no journal, , 

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. Last year, we built the scale-down heat removal test facility and now conduct experiments to understand the heat-transfer characteristics. As a result, we could assess effect of radiation quantitatively for passive decay heat removal from the RPV.

Oral presentation

Study on heat transfer characteristics of reactor cavity cooling system with passive safety features; Experimental investigation using a scaled model

Yamaguchi, Shuhei*; Sato, Noriyasu*; Matsumoto, Tatsuya*; Morita, Koji*; Takamatsu, Kuniyoshi

no journal, , 

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. In 205, we built the scale-down heat removal test facility and now conduct experiments to understand the heat-transfer characteristics. As a result, we could assess effect of radiation quantitatively for passive decay heat removal from the RPV.

12 (Records 1-12 displayed on this page)
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