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Journal Articles

Toward mechanistic evaluation of critical heat flux in nuclear reactors, 2; Recent studies and future challenges toward mechanistic and reliable CHF evaluation

Okawa, Tomio*; Mori, Shoji*; Liu, W.*; Ose, Yasuo*; Yoshida, Hiroyuki; Ono, Ayako

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(12), p.820 - 824, 2021/12

https://doi.org/10.3327/jaesjb.63.12_820

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.

JAEA Reports

Research on the fundamental process of thermal-hydraulic behaviors in severe accident; Heat transfer on the liquid-liquid interface between molten core pool and coolant, JAERI's nuclear research promotion program, H10-027-6 (Contract research)

Mishima, Kaichiro*; Saito, Yasushi*

JAERI-Tech 2002-014, 83 Pages, 2002/03

JAERI-Tech-2002-014.pdf:6.83MB

no abstracts in English

Journal Articles

Experiments on heat transfer of smooth and swirl tubes under one-sided heating conditions

Araki, Masanori; Ogawa, Masuro; Kunugi, Tomoaki; Sato, Kazuyoshi;

Int. J. Heat Mass Transfer, 39(14), p.3045 - 3055, 1996/00

https://doi.org/10.1016/0017-9310(95)00344-4
 Times Cited Count：73 Percentile：93.86(Thermodynamics)

no abstracts in English

Journal Articles

Experimental study of incipient nucleate boiling in narrow vertical rectangular channel simulating subchannel of upgraded JRR-3

Sudo, Yukio; ; ; Kaminaga, Masanori

Journal of Nuclear Science and Technology, 23(1), p.73 - 82, 1985/00

https://doi.org/10.3327/jnst.23.73
 Times Cited Count：36 Percentile：94.24(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Thermal-Hydraulic Analyses of the JMTR and the JRR-2 with LEU Fuels

JAERI-M 9449, 30 Pages, 1981/04

JAERI-M-9449.pdf:0.79MB

no abstracts in English

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