JOPSS - Search Results

Journal Articles

Estimation of the core degradation and relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 based on RELAP/SCDAPSIM analysis

Madokoro, Hiroshi; Sato, Ikken

Nuclear Engineering and Design, 376, p.111123_1 - 111123_15, 2021/05

https://doi.org/10.1016/j.nucengdes.2021.111123

Times Cited Count：12 Percentile：72.22(Nuclear Science & Technology)

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

Analyses of ALPHA in-vessel debris coolability experiments with SCDAPSIM code

Hidaka, Akihide; Maruyama, Yu; Ueno, Shingo*; Sugimoto, Jun

JAERI-Conf 99-005, p.49 - 55, 1999/07

https://doi.org/10.11484/jaeri-conf-99-005

no abstracts in English

Journal Articles

Analytical study on depressurization during PWR station blackout

Hidaka, Akihide; Ezzidi, A.*; Sugimoto, Jun

PSA 96: Int. Topical Meeting on Probabilistic Safety Assessment, 3, p.1548 - 1556, 1996/00

no abstracts in English

Journal Articles

SCDAP/RELAP5 analysis of station blackout with pump seal LOCA in Surry plant

Hidaka, Akihide; Soda, Kunihisa; Sugimoto, Jun

Journal of Nuclear Science and Technology, 32(6), p.527 - 538, 1995/06

https://doi.org/10.3327/jnst.32.527

Times Cited Count：3 Percentile：35.96(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Vectorization and improvement of nuclear codes; MEUDAS4, FORCE, STREAM V2.6, HEATING7-VP, SCDAP/RELAP5/MOD2.5, NBI3DGFN

; ; ; ; ; Yokokawa, Mitsuo

JAERI-M 92-142, 117 Pages, 1992/09

JAERI-M-92-142.pdf:2.45MB

no abstracts in English

Journal Articles

Hydrogen generation during reflooding of degraded core as an accident management measure

Hidaka, Akihide; Sugimoto, Jun; Soda, Kunihisa

EUR-14039-EN, p.28 - 36, 1992/00

no abstracts in English

Journal Articles

Quenching degradation in-pile experiment on an oxidized fuel rod in the temperature range of 1000 to 1260 $^{circ}$ C

Katanishi, Shoji; Sobajima, Makoto;

Nucl. Eng. Des., 132, p.239 - 251, 1991/00

https://doi.org/10.1016/0029-5493(91)90268-M

Times Cited Count：4 Percentile：47.15(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Sensitivity analyses on reflooding effect on the TMI-2 accident by the SCDAP code

Hidaka, Akihide; Sugimoto, Jun; ; Soda, Kunihisa

JAERI-M 89-213, 87 Pages, 1989/12

JAERI-M-89-213.pdf:1.66MB

no abstracts in English

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Estimation of the core degradation and relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 based on RELAP/SCDAPSIM analysis

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

Analyses of ALPHA in-vessel debris coolability experiments with SCDAPSIM code

Analytical study on depressurization during PWR station blackout

SCDAP/RELAP5 analysis of station blackout with pump seal LOCA in Surry plant

Vectorization and improvement of nuclear codes; MEUDAS4, FORCE, STREAM V2.6, HEATING7-VP, SCDAP/RELAP5/MOD2.5, NBI3DGFN

Hydrogen generation during reflooding of degraded core as an accident management measure

Quenching degradation in-pile experiment on an oxidized fuel rod in the temperature range of 1000 to 1260 $^{circ}$ C

Sensitivity analyses on reflooding effect on the TMI-2 accident by the SCDAP code