Depressurization effects of vacuum vessel pressure supression systems in fusion reactors at multiple first wall pipe break events

Takase, Kazuyuki; Akimoto, Hajime

Applied Electromagnetics in Materials, p.177 - 178, 2001/00

no abstracts in English

Numerical analysis on ingress-of-coolant events in fusion reactors with TRAC-PF1 code

Ose, Yasuo*; Takase, Kazuyuki; Akimoto, Hajime

JAERI-Research 99-075, p.95 - 0, 2000/01

JAERI-Research-99-075.pdf:4.62MB

no abstracts in English

Analyses of accident events on thermal-hydraulics in fusion reactor design

Takase, Kazuyuki; Ose, Yasuo*; Akimoto, Hajime

Nihon Kikai Gakkai Kansai Shibu Dai-75-ki Teiji Soukai Koenkai Koen Rombunshu, p.13_11 - 13_12, 2000/00

no abstracts in English

Analytical study on effect of reactor depressurization measures during LOCA sequences followed by loss of HPI in PWRs

Watanabe, Norio; ; ; Kumamaru, Hiroshige; Hirano, Masashi

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1303 - 1310, 1995/00

no abstracts in English

Analyses of the Mihama-2 SGTR event and ROSA-IV experiment SB-SG-06 to simulate the event

Hirano, Masashi; Watanabe, Tadashi

Proc. of the 5th Int. Topical Meeting on Reactor Thermal Hydraulics: NURETH-5,Vol. 1, p.165 - 173, 1992/00

no abstracts in English

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

https://doi.org/10.3327/jnst.28.33

no abstracts in English

Improvement of numerical treatment of convection term in TRAC-PF1 code at transition from single phase flow to two phase flow

Abe, Yutaka; ; Onuki, Akira; Murao, Yoshio; Kamo, Hideki*

Proc. of the Int. Conf. on Multiphase Flows 91-TSUKUBA,Vol. 2, p.373 - 376, 1991/00

no abstracts in English

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

Evaluation of interfacial shear model for bubbly flow regime with the MINCS code

Hirano, Masashi; ; ; ; ; ; ;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.1 - 80, 1986/00

no abstracts in English