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Okawa, Tomio*; Mori, Shoji*; Liu, W.*; Ose, Yasuo*; Yoshida, Hiroyuki; Ono, Ayako
Nihon Genshiryoku Gakkai-Shi ATOMO
, 63(12), p.820 - 824, 2021/12
The evaluation method of the critical heat flux based on the mechanism is needed for the efficient design and development of fuel in reactors and the appropriate safety evaluation. In this paper, the current researches relating to the mechanism of the critical heat flux are reviewed, and the issue to be considered in the future are discussed.
Sato, Ikken
Journal of Nuclear Science and Technology, 56(5), p.394 - 411, 2019/05
Times Cited Count：5 Percentile：75.46(Nuclear Science & Technology)Water columns were adopted in the pressure measurement system of Fukushima-Daiichi Unit-3. Part of these water columns evaporated during the accident condition jeopardizing correct understanding on actual pressure. Through comparison of RPV (Reactor Pressure Vessel) and S/C pressures with D/W pressure, such water-column effect was evaluated. Correction for this effect was developed enabling clarification of slight pressure difference among RPV, S/C and D/W. This information was then integrated with other available data such as, water level, CAMS and environmental dose rate, into an interpretation of accident focusing on RPV and PCV pressurization/depressurization and radioactive material release to environment. It is suggested that dryout of in-vessel and ex-vessel debris was likely causing pressure decrease. S/C water poured into pedestal heated by relocated debris was the likely cause of pressurization. Cyclic reflooding of pedestal debris and dryout was likely.
Ono, Ayako; Suzuki, Takayuki*; Yoshida, Hiroyuki
Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) (USB Flash Drive), 9 Pages, 2018/10
The mechanism of Critical Heat Flux (CHF) remains to be clarified, even though it is important to evaluate the CHF for super high heat flux components such as light water reactors (LWRs). Some theoretical models to predict the CHF is proposed so far. A macrolayer formation model which is proposed in order to predict the CHF based on the macrolayer dryout model. In this model, it is assumed that the liquid is captured inside vapor mass at coalescence. In this study, the verification of the assumption of a macrolayer formation model by the numerical simulation of CMFD code, TPFIT, from the view point of hydrodynamics.
Guo, Z.*; Kumamaru, Hiroshige; Kukita, Yutaka
JAERI-M 93-238, 20 Pages, 1993/12
no abstracts in English
Ezzidi, A.*; Okubo, Tsutomu; Murao, Yoshio
JAERI-M 93-133, 39 Pages, 1993/07
no abstracts in English
Okubo, Tsutomu; Ezzidi, A.*; Murao, Yoshio
JAERI-M 93-069, 115 Pages, 1993/03
no abstracts in English
Kumamaru, Hiroshige; Kukita, Yutaka
Nucl. Eng. Des., 144, p.257 - 268, 1993/00
Times Cited Count：1 Percentile：19.22(Nuclear Science & Technology)no abstracts in English
Kumamaru, Hiroshige; Kukita, Yutaka
ANP 92: Proc. of the Int. Conf. on Design and Safety of Advanced Nuclear Power Plants,Vol. 3, p.24.4-1 - 24.4-7, 1992/00
no abstracts in English
Kumamaru, Hiroshige; Kukita, Yutaka
ANS Proc. 1991 National Heat Transfer Conf., Vol. 5, p.22 - 29, 1991/00
no abstracts in English
Kumai, Toshio; *; ; Akutsu, Cho; Takahashi, Hidetake
JAERI-M 89-114, 32 Pages, 1989/09
no abstracts in English
Kumamaru, Hiroshige; Koizumi, Yasuo; Tasaka, Kanji
Journal of Nuclear Science and Technology, 26(5), p.544 - 557, 1989/05
no abstracts in English
Kumamaru, Hiroshige; Koizumi, Yasuo; Tasaka, Kanji
Journal of Nuclear Science and Technology, 25(2), p.207 - 209, 1988/00
no abstracts in English
Journal of Nuclear Science and Technology, 24(10), p.811 - 820, 1987/10
Times Cited Count：4 Percentile：45.75(Nuclear Science & Technology)no abstracts in English
Osakabe, Masahiro; Christian Chauliac*; ; Koizumi, Yasuo; ; Tasaka, Kanji
Journal of Nuclear Science and Technology, 24(2), p.103 - 110, 1987/02
Times Cited Count：9 Percentile：67.55(Nuclear Science & Technology)no abstracts in English
Koizumi, Yasuo; ; Tasaka, Kanji
Journal of Nuclear Science and Technology, 24(1), p.61 - 74, 1987/01
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
; Koizumi, Yasuo; Tasaka, Kanji
Nucl.Eng.Des., 102, p.71 - 84, 1987/00
Times Cited Count：18 Percentile：83.98(Nuclear Science & Technology)no abstracts in English
Koizumi, Yasuo; ; ; Tasaka, Kanji
Nucl.Eng.Des., 99, p.157 - 165, 1987/00
Times Cited Count：10 Percentile：70.71(Nuclear Science & Technology)no abstracts in English
Abe, Yutaka; Sudo, Yukio
Journal of Nuclear Science and Technology, 21(12), p.962 - 964, 1984/00
Times Cited Count：7 Percentile：82.14(Nuclear Science & Technology)no abstracts in English
Koizumi, Yasuo; ; Tasaka, Kanji
Journal of Nuclear Science and Technology, 21(12), p.965 - 968, 1984/00
Times Cited Count：3 Percentile：60.12(Nuclear Science & Technology)no abstracts in English
Koizumi, Yasuo; Tasaka, Kanji
Journal of Nuclear Science and Technology, 19(12), p.965 - 984, 1982/00
Times Cited Count：8 Percentile：66.47(Nuclear Science & Technology)no abstracts in English
Ono, Ayako; Sakashita, Hiroto*
no journal, ,
A macrolayer formation model for saturated and subcooled pool boiling is proposed, which is developed based on the visual observation of boiling behavior. The distribution of nucleation sites is assumed to distribute based on Poisson distribution. The predicted macrolayer thicknesses are used for the prediction of CHFs in saturated and subcooled pool boiling based on the macrolayer dryout model. The combination of the macrolayer dryout model and macrolayer formation model is able to predict the CHF well at least up to subcooling 40K.
