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Journal Articles

Numerical study on modeling of liquid film flow under countercurrent flow limitation in volume of fluid method

Watanabe, Taro*; Takata, Takashi; Yamaguchi, Akira*

Nuclear Engineering and Design, 313, p.447 - 457, 2017/03

 Times Cited Count:1 Percentile:15.39(Nuclear Science & Technology)

Countercurrent flow limitation (CCFL) in a heat transfer tube at a steam generator (SG) of pressurized water reactor (PWR) is one of the important issues on the core cooling under a loss of coolant accident(LOCA). In order to improve the prediction accuracy of the CCFL characteristics in numerical simulations using the volume of fluid (VOF) method with less computational cost, a thin liquid film flow in a countercurrent flow is modeled independently and is coupled with the VOF method. Then, we have carried out numerical simulations of a countercurrent flow in a vertical tube so as to investigate the CCFL characteristics and compare them with the previous experimental results. As a result, it has been concluded that the effect of liquid film entrainment by upward gas flux will cause the difference in the experiments.

JAEA Reports

Study on thermal-hydraulics during a PWR reflood phase

Iguchi, Tadashi

JAERI-Research 98-054, 216 Pages, 1998/10

JAERI-Research-98-054.pdf:7.94MB

no abstracts in English

Journal Articles

Analytical study on characteristics of falling water limitation in countercurrent two-phase flow in vertical annular channels

Sudo, Yukio

Nihon Kikai Gakkai Rombunshu, B, 60(576), p.2888 - 2894, 1994/08

no abstracts in English

JAEA Reports

Evaluation report on SCTF-III test S3-3, S3-4 and S3-5; Counter current flow limitation phenomena in full radius core

Iguchi, Tadashi; *; Iwamura, Takamichi; ; Okubo, Tsutomu; Onuki, Akira; *; Murao, Yoshio

JAERI-M 91-172, 154 Pages, 1991/10

JAERI-M-91-172.pdf:3.19MB

no abstracts in English

JAEA Reports

Estimation of shear stress in counter-current gas-liquid annular two-phase flow

Abe, Yutaka; ; Murao, Yoshio

JAERI-M 90-215, 81 Pages, 1991/01

JAERI-M-90-215.pdf:2.5MB

no abstracts in English

Journal Articles

CCFL characteristics of PWR steam generator U-tubes

Yonomoto, Taisuke; Anoda, Yoshinari; Kukita, Yutaka; Y.Peng*

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.522 - 529, 1991/00

no abstracts in English

JAEA Reports

Journal Articles

Experimental study of counter-current two-phase flow in horizontal tube connected to inclined riser

Journal of Nuclear Science and Technology, 23(3), p.219 - 232, 1986/00

no abstracts in English

Journal Articles

Two-dimensional fall back flow and core cooling in the slab core test facility: SCTF

; ; ;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 129, 1986/00

no abstracts in English

Journal Articles

Initial thermal-hydraulic bebaviors under simultaneous ECC water injection into cold leg and upper plenum in a PWR-LOCA

;

Journal of Nuclear Science and Technology, 22(6), p.451 - 460, 1985/00

 Times Cited Count:1 Percentile:24.56(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Effects of Upper Plenum Injection on Thermo-Hydrodynamic Behavior under Refill and Reflood Phases

; ; Abe, Yutaka; ; ; Osakabe, Masahiro

JAERI-M 84-221, 151 Pages, 1984/12

JAERI-M-84-221.pdf:3.43MB

no abstracts in English

Journal Articles

Spray cooling test; A separate effect test with ROSA-III,a BWR-LOCA simulation facility

Journal of Nuclear Science and Technology, 18(8), p.629 - 639, 1981/00

 Times Cited Count:3 Percentile:46.22(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Sensitivity Analysis of ROSA-III Test RUN 704 Using RELAP4J Code

*; Tasaka, Kanji

JAERI-M 9156, 40 Pages, 1980/11

JAERI-M-9156.pdf:1.63MB

no abstracts in English

JAEA Reports

DATAREPORTONSPRAYCOOLINGTESTBYTHEROSA-III,1

; ;

JAERI-M 8760, 195 Pages, 1980/03

JAERI-M-8760.pdf:5.12MB

no abstracts in English

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