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Takeda, Takeshi; Otsu, Iwao
Science and Technology of Nuclear Installations, 2018, p.7635878_1 - 7635878_19, 2018/00
Times Cited Count：2 Percentile：23.76(Nuclear Science & Technology)Doda, Norihiro; Hiyama, Tomoyuki; Tanaka, Masaaki; Ohshima, Hiroyuki; Thomas, J.*; Vilim, R. B.*
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 10 Pages, 2017/06
In sodium-cooled fast reactors, a natural circulation is expected to remove the core decay heat when the plant gets into a station blackout. From a perspective of reactor safety, the core hot spot temperature arising in the natural circulation should be evaluated accurately. To this end, Japan Atomic Energy Agency is trying to couple a 1-D plant dynamics analysis code Super-COPD and a 3-D CFD code AQUA to solve the thermal-hydraulic field in the whole plant under natural circulation condition. As a validation study, the coupled code was applied to an analysis of EBR-II shutdown heat removal test. The obtained numerical results reasonably agreed with the measured data, which demonstrated the validity of the coupled code.
Chikazawa, Yoshitaka; Kato, Atsushi; Hayafune, Hiroki; Shimakawa, Yoshio*; Kamishima, Yoshio*
Nuclear Technology, 192(2), p.111 - 124, 2015/11
Times Cited Count：1 Percentile：10.17(Nuclear Science & Technology)Evaluation of severe external hazards on JSFR has been analyzed. For seismic design, safety components are confirmed to maintain their functions even against recent strong earthquakes. For tsunam, hypothetical station blackout has been evaluated.
Takeda, Takeshi; Otsu, Iwao
Mechanical Engineering Journal (Internet), 2(5), p.15-00132_1 - 15-00132_15, 2015/10
Takeda, Takeshi; Otsu, Iwao
Journal of Energy and Power Sources, 2(7), p.274 - 290, 2015/07
Takeda, Takeshi; Otsu, Iwao
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 10 Pages, 2015/05
Hidaka, Akihide; Maruyama, Yu; Nakamura, Hideo
Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 15 Pages, 2004/00
Severe accident studies showed that Direct Containment Heating issue was resolved for PWRs because a creep rupture at pressurizer surge line would occur prior to the melt-through of Reactor Pressure Vessel during station blackout (TMLB'). However, it was recently concerned that, if the secondary system is depressurized during TMLB', the creep rupture at SG U-tubes would occur earlier than the surge line. This pressure- and temperature-induced SG U-tube rupture (PTI-SGTR) is not preferable because of the increase in offsite consequences. The SCDAP/RELAP5 analyses by USNRC showed that the surge line would fail earlier than the U-tubes. However, the analyses used a coarse nodilization for steam mixing at the SG inlet plenum that could affect the temperature of U-tubes. To investigate the effect of steam mixing, an analysis was performed with MELCOR1.8.4. The analysis showed that the surge line would fail earliest during TMLB' while the U-tubes could fail earliest during TMLB' with secondary system depressurization. Further investigation is needed for occurrence conditions of PTI-SGTR.
Suzuki, Mitsuhiro
JAERI-Tech 2002-071, 171 Pages, 2002/10
JAERI-Tech-2002-071.pdf:11.26MB
no abstracts in English
Hidaka, Akihide; Soda, Kunihisa; Sugimoto, Jun
Journal of Nuclear Science and Technology, 32(6), p.527 - 538, 1995/06
Times Cited Count：2 Percentile：28.33(Nuclear Science & Technology)no abstracts in English
Anoda, Yoshinari; Katayama, Jiro*; Kukita, Yutaka; R.Mandl*
Power Plant Transients,1992; FED-Vol. 140, p.89 - 96, 1993/00
no abstracts in English
Kukita, Yutaka; Anoda, Yoshinari; ; F.Serre*
Power Plant Transients; 1990, p.7 - 14, 1991/00
no abstracts in English
*; Iwamura, Takamichi; Okubo, Tsutomu; ; Murao, Yoshio
JAERI-M 90-047, 37 Pages, 1990/03
no abstracts in English
; ; ; *; *
Source Term Evaluation for Accident Conditions, p.733 - 744, 1986/00
no abstracts in English
; *; ; *
Nihon Genshiryoku Gakkai-Shi, 27(1), p.56 - 65, 1985/00
Times Cited Count：1 Percentile：24.26(Nuclear Science & Technology)no abstracts in English
