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JAEA Reports

Literature survey of thermal-hydraulic studies on super-critical pressurized water

Kurihara, Ryoichi; Watanabe, Kenichi*; Konishi, Satoshi

JAERI-Review 2003-020, 37 Pages, 2003/07

JAERI-Review-2003-020.pdf:2.08MB

no abstracts in English

Journal Articles

Experimental study on cooling limit under flow instability in boiling flow channel

Iguchi, Tadashi; Shibamoto, Yasuteru; Asaka, Hideaki; Nakamura, Hideo

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 8 Pages, 2003/04

Authors investigated the cooling limit under flow instability, by conducting THYNC experiments using a 2$$times$$2 bundle test section of electrical rod heaters、whose heated lengths and diameters were 3.71m and 12.3mm. The experimental result indicated periodic rise and rapid drop of the rod temperature under flow oscillation, indicating periodic film boiling. When the heating power increased further, the rod temperature indicated continuous film boiling. The power at the onset of continuous film boiling (cooling limit) under flow oscillation was about 50%-80% of the cooling limit under steady flow condition in THYNC. The ratio of both cooling limits almost agreed with the Umekawa model prediction in cases of P$$<$$2MPa and G$$<$$400kg/m2s. For high pressure and high mass flux conditions, the ratio almost agreed with the empirical model based on the heat balance during one cycle of flow oscillation. TRAC-BF1 code simulated periodic film boiling qualitatively, but the cooling limit under the flow oscillation was not predicted well probably due to inaccurate rewetting prediction.

Journal Articles

Numerical analysis on ingress of coolant event in vacuum vessel using modified TRAC-BF1

Kurihara, Ryoichi; Ajima, Toshio*; Ueda, Shuzo; Seki, Yasushi

Journal of Nuclear Science and Technology, 38(7), p.571 - 576, 2001/07

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

no abstracts in English

JAEA Reports

Analysis for ingress of coolant event in vacuum vessel using modified TRAC-BF1 code

Ajima, Toshio*; Kurihara, Ryoichi; Seki, Yasushi

JAERI-Data/Code 99-040, 84 Pages, 1999/08

JAERI-Data-Code-99-040.pdf:2.75MB

no abstracts in English

JAEA Reports

Vectorization, parallelization and porting of nuclear codes on the VPP500 system (Porting); Progress report fiscal 1997

*; *; *; *; *; Adachi, Masaaki*; Ogasawara, Shinobu*; *; Kume, Etsuo

JAERI-Data/Code 99-027, 39 Pages, 1999/05

JAERI-Data-Code-99-027.pdf:1.21MB

no abstracts in English

JAEA Reports

Development of input data for thermal-hydraulic computer code TRAC-BF1 for analyses of 1,100MW BWRs

*; Watanabe, Norio; Hirano, Masashi

JAERI-Data/Code 98-037, 193 Pages, 1998/11

JAERI-Data-Code-98-037.pdf:6.14MB

no abstracts in English

Journal Articles

Analysis and experimental results on ingress of coolant event in vacuum vessel

Kurihara, Ryoichi; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Shibata, Mitsuhiko; Seki, Yasushi; *; Yamauchi, Michinori*; *; *

Fusion Engineering and Design, 42, p.61 - 66, 1998/00

 Times Cited Count:7 Percentile:53.8(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Improvement of TRAC-BF1 code to analyze the ingress of coolant event (ICE)

Ajima, Toshio*; Kurihara, Ryoichi; Seki, Yasushi; *; Yamauchi, Michinori*

JAERI-Data/Code 97-034, 77 Pages, 1997/08

JAERI-Data-Code-97-034.pdf:1.71MB

no abstracts in English

Journal Articles

A Study of interfacial friction model for upward flow in vertical pipe at low mass velocity

; Onuki, Akira; Abe, Yutaka; Murao, Yoshio

Proc. of the Int. Conf. on Multiphase Flows 91-TSUKUBA, p.369 - 372, 1991/00

no abstracts in English

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