Refine your search:     
Report No.
 - 
Search Results: Records 1-16 displayed on this page of 16
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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:2 Percentile:19.65(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:24.17(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:45.64(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

16 (Records 1-16 displayed on this page)
  • 1