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Journal Articles

Pool-boiling/bubbling void fraction in an annular flow channel

*; Kumamaru, Hiroshige; *; *; Tasaka, Kanji

Nucl. Eng. Des., 132, p.381 - 391, 1992/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Temporary core liquid level depression during a cold-leg small-break loss-of-coolant accident; The effect of break size and power level

*; Kumamaru, Hiroshige; *; Kukita, Yutaka; *

Nuclear Technology, 96, p.290 - 301, 1991/12

 Times Cited Count:5 Percentile:53.89(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Improvement of TRAC-PFl interfacial drag model for analysis of high-pressure horizontally-stratified two-phase flow

; Kukita, Yutaka; Anoda, Yoshinari; Nakamura, Hideo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 28(1), p.33 - 44, 1991/01

no abstracts in English

JAEA Reports

Developmental assessment of RELAP5/MOD3 code against ROSA-IV/TPTF horizontal two-phase flow experiments

Kukita, Yutaka; ; *; Anoda, Yoshinari; ; ; Tasaka, Kanji

JAERI-M 90-053, 22 Pages, 1990/03

JAERI-M-90-053.pdf:0.6MB

no abstracts in English

Journal Articles

Interfacial drag coefficient of air-water mixture in rod bundle

Osakabe, Masahiro; Koizumi, Yasuo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 21(11), p.882 - 884, 1984/00

 Times Cited Count:15 Percentile:91.37(Nuclear Science & Technology)

no abstracts in English

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