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Journal Articles

Secondary-side depressurization during PWR cold-leg small break LOCAs based on ROSA-V/LSTF experiments and analyses

Asaka, Hideaki; Anoda, Yoshinari; Kukita, Yutaka*;

Journal of Nuclear Science and Technology, 35(12), p.905 - 915, 1998/12

 Times Cited Count:15 Percentile:76.16(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Vectorization, parallelization and porting of nuclear codes on the VPP500 system, porting; Progress report fiscal 1996

*; *; *; *; *; *; Harada, Hiro; ; Kume, Etsuo;

JAERI-Data/Code 97-055, 161 Pages, 1998/01

JAERI-Data-Code-97-055.pdf:4.57MB

no abstracts in English

Journal Articles

RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following sblocas with totally failed HPI

*; Kukita, Yutaka*; Asaka, Hideaki; M.Wang*; Otani, Etsuo*

Nuclear Technology, 126(3), p.331 - 339, 1998/00

 Times Cited Count:9 Percentile:58.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

PWR small break Loss-of-Coolant-Accident Experiment at ROSA-V/LSTF with a combination of secondary-side depressurization and gravity-driven safety injection

Yonomoto, Taisuke; ; Kukita, Yutaka

Journal of Nuclear Science and Technology, 34(6), p.571 - 581, 1997/06

 Times Cited Count:5 Percentile:43.99(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of wall heat capacity effects on core makeup tank drain-down behavior in ROSA/AP600 experiments

; Yonomoto, Taisuke; ; Kukita, Yutaka*; R.Schultz*

Proc. of 1997 Int. Meeting on Advanced Reactors Safety, 0, p.217 - 224, 1997/06

no abstracts in English

Journal Articles

Analysis of ROSA-IV/LSTF 10% main steam line break test RUN SB-SL-01 using RELAP5/MOD3

H.Lee*; H.Seong*; G.Park*; Kumamaru, Hiroshige; Kukita, Yutaka

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 3, p.41 - 50, 1996/00

no abstracts in English

Journal Articles

RELAP5/MOD3 code analyses of LSTF tests on intentional primary system depressurization following PWR small-break LOCA

Kumamaru, Hiroshige; ; M.Wang*; Kukita, Yutaka

Validation of Systems Transients Analysis Codes (FED-Vol. 223), 0, p.129 - 136, 1995/00

no abstracts in English

Journal Articles

Experiment and analyses of PWR station blackout transient involving pump seal leak

Watanabe, Tadashi; Kukita, Yutaka

Proc. of the 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 2, p.1232 - 1239, 1993/00

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

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