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Journal Articles

Dimensional analysis of critical heat flux in subcooled water flow under one-side heating conditions for fusion application

J.Boscary*; Araki, Masanori; J.Schlosser*; Akiba, Masato; F.Escorbiac*

Fusion Engineering and Design, 43(2), p.147 - 171, 1998/00

https://doi.org/10.1016/S0920-3796(98)00387-1
 Times Cited Count：44 Percentile：93.84(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Critical heat flux of forced flow boiling in a narrow one-side heated rectangular flow channel

L.Zheng*; Iguchi, Tadashi; Kureta, Masatoshi; Akimoto, Hajime

JAERI-Research 97-054, 85 Pages, 1997/08

JAERI-Research-97-054.pdf:2.18MB

no abstracts in English

Journal Articles

CHF experiments under steady-state and transient conditions for tight lattice core with non-uniform axial power distribution

Iwamura, Takamichi; Watanabe, Hironori; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 30(5), p.413 - 424, 1993/05

https://doi.org/10.3327/jnst.30.413
 Times Cited Count：2 Percentile：29.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of subchannel code to DNB analysis of HCLWR

Iwamura, Takamichi; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio

Subchannel Analysis in Nuclear Reactors, p.281 - 301, 1992/00

no abstracts in English

JAEA Reports

Critical heat flux experiments for high conversion light water reactor, 3; Heated length: 0.5$$sim$$1.0m, P/D: 1.126$$sim$$1.2, number of rods: 4$$sim$$7

Iwamura, Takamichi; Okubo, Tsutomu; *; ; Murao, Yoshio

JAERI-M 90-044, 158 Pages, 1990/03

JAERI-M-90-044.pdf:2.81MB

no abstracts in English

JAEA Reports

Study of Transient Burnout Characteristics under Flow Reduction Condition

;

JAERI 1290, 42 Pages, 1984/03

JAERI-1290.pdf:2.2MB

no abstracts in English

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