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JAEA Reports

Evaluation of steam generator U-tube integrity during PWR station blackout with secondary system depressurization

Hidaka, Akihide; Asaka, Hideaki; Ueno, Shingo*; Yoshino, T.*; Sugimoto, Jun

JAERI-Research 99-067, p.55 - 0, 1999/12

JAERI-Research-99-067.pdf:2.51MB

no abstracts in English

Journal Articles

Experimental study on buoyancy-driven exchange flows through breaches of a tokamak vacuum vessel of a fusion reactor under the loss-of-vacuum-event condition

Takase, Kazuyuki; Kunugi, Tomoaki; Ogawa, Masuro; Seki, Yasushi

Nuclear Science and Engineering, 125(2), p.223 - 231, 1997/00

 Times Cited Count:11 Percentile:65.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effects of breach area and length to exchange flow rates under the LOVA condition in a fusion reactor

Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi

Fusion Technology, 30(3(PT.2B)), p.1459 - 1464, 1996/12

no abstracts in English

Journal Articles

Limitation of falling water in countercurrent two-phase flow in vertical circular tubes

Sudo, Yukio

Nihon Kikai Gakkai Rombunshu, B, 60(575), p.2566 - 2572, 1994/07

no abstracts in English

Journal Articles

Study on flow rate measurement of buoyancy-driven exchange flow by laser Doppler velocimeter

Fumizawa, Motoo; Hishida, Makoto; Inagaki, Yoshiyuki

Proc. of the 5th Int. Topical Meeting on Reactor Thermal Hydraulics, p.369 - 376, 1992/00

no abstracts in English

Journal Articles

Estimation of shear stress in counter current annular flow

Abe, Yutaka; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 28(3), p.208 - 217, 1991/03

no abstracts in English

Journal Articles

Analysis of interfacial and wall friction factors of counter-current flow in vertical pipe

Abe, Yutaka; ; Murao, Yoshio

6th Proc. of Nuclear Thermal Hydraulics, p.401 - 408, 1990/11

no abstracts in English

Journal Articles

Analysis of interfacial and wall friction factors of countercurrent flow in vertical pipes

Abe, Yutaka; ; Murao, Yoshio

Transactions of the American Nuclear Society, 62, p.719 - 720, 1990/11

no abstracts in English

Journal Articles

Experimental study on flow behavior at horizontal opening in the unstably stratified fluid

Fumizawa, Motoo; Ogawa, Masuro; Hishida, Makoto

Nihon Genshiryoku Gakkai-Shi, 31(10), p.1127 - 1127, 1989/10

 Times Cited Count:3 Percentile:59.56(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Journal Articles

Upper plenum dump during reflood in PWR loss-of-coolant accident

Sudo, Yukio; P.Griffith*

Journal of Nuclear Science and Technology, 18(7), p.487 - 500, 1981/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Counter current flow limiting in inclined pipe simulating PWR hot-leg

Satou, Akira; Shibamoto, Yasuteru; Yonomoto, Taisuke

no journal, , 

Experiments were conducted to investigate the phenomena and modelize the onset condition of counter-current flow limiting (CCFL) in the hot leg of PWR under an accident. Scaling effects were investigated using two test parts with different diameters, and the onset condition of CCFL were comprehended focusing on two kinds of CCFL.

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