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Journal Articles

Estimation of long-term ex-vessel debris cooling behavior in Fukushima Daiichi Nuclear Power Plant unit 3

Sato, Ikken; Yamaji, Akifumi*; Li, X.*; Madokoro, Hiroshi

Mechanical Engineering Journal (Internet), 9(2), p.21-00436_1 - 21-00436_17, 2022/04

https://doi.org/10.1299/mej.21-00436

Journal Articles

Assessment of REFLA/TRAC code for system behavior during reflood phase in a PWR LOCA with CCTF data

; Onuki, Akira; Murao, Yoshio

Proc. of the 2nd Int. Conf. on Multiphase Flow 95-Kyoto, 0, p.P2_37 - P2_44, 1995/00

no abstracts in English

JAEA Reports

Void fraction in a PWR fuel bundle during reflood phase; Evaluation of equivalent diameter effect by air water test

Iguchi, Tadashi

JAERI-M 94-008, 32 Pages, 1994/02

JAERI-M-94-008.pdf:0.86MB

no abstracts in English

Journal Articles

Elimination of numerical pressure spikes induced by two-fluid model

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

Journal of Nuclear Science and Technology, 30(12), p.1214 - 1224, 1993/12

https://doi.org/10.3327/jnst.30.1214
 Times Cited Count：3 Percentile：38.58(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Assessment of TRAC-PF1/MOD1 code for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with a radial power distribution

Onuki, Akira; ; Murao, Yoshio

JAERI-M 93-139, 85 Pages, 1993/07

JAERI-M-93-139.pdf:1.79MB

no abstracts in English

JAEA Reports

Assessment of TRAC-PF1/MOD1 and TRAC-PF1/MOD2 codes for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with an inclined radial power distribution

Onuki, Akira; ; Murao, Yoshio

JAERI-M 93-138, 55 Pages, 1993/07

JAERI-M-93-138.pdf:1.31MB

no abstracts in English

JAEA Reports

Assessment of TRAC-BF1 1D reflood model with CCTF and SCTF data

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

JAERI-M 93-045, 126 Pages, 1993/03

JAERI-M-93-045.pdf:2.56MB

no abstracts in English

JAEA Reports

Assessment of TRAC-PF1/MOD1 code for core thermal hydraulic behavior during reflood with CCTF and SCTF data

; Onuki, Akira; *; Murao, Yoshio

JAERI-M 93-032, 190 Pages, 1993/03

JAERI-M-93-032.pdf:3.0MB

no abstracts in English

JAEA Reports

Implementation of JAERIs reflood model into TRAC-PF1/MOD1 code

; Onuki, Akira; Murao, Yoshio

JAERI-M 93-027, 66 Pages, 1993/02

JAERI-M-93-027.pdf:1.65MB

no abstracts in English

Journal Articles

Large-scale multi-dimensional phenomena found in CCTF and SCTF experiments

Murao, Yoshio; Iguchi, Tadashi; ; Iwamura, Takamichi

Nucl. Eng. Des., 145, p.85 - 95, 1993/00

https://doi.org/10.1016/0029-5493(93)90060-M
 Times Cited Count：4 Percentile：45.45(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Modeling of reflooding

G.Yadigaroglu*; R.A.Nelson*; V.Teschendorff*; Murao, Yoshio; J.Kelly*; D.Bestion*

Nucl. Eng. Des., 145, p.1 - 35, 1993/00

https://doi.org/10.1016/0029-5493(93)90056-F
 Times Cited Count：23 Percentile：87.95(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study of two-phase flow under low velocity in PWR-LOCA

Onuki, Akira

JAERI-M 92-150, 134 Pages, 1992/10

JAERI-M-92-150.pdf:4.08MB

no abstracts in English

Journal Articles

Development of reflood model for two fluid model code based on physical models used in REFLA code

; Murao, Yoshio

Journal of Nuclear Science and Technology, 29(7), p.642 - 655, 1992/07

https://doi.org/10.3327/jnst.29.642

no abstracts in English

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-5(Run 63); Effect of decay heat level on PWR reflood phenomena

Iguchi, Tadashi; ; Okabe, Kazuharu*; Sugimoto, Jun; ; Okubo, Tsutomu; Murao, Yoshio

JAERI-M 91-174, 98 Pages, 1991/10

JAERI-M-91-174.pdf:2.31MB

no abstracts in English

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-1(Run 55); Effect of pressure on reflood phenomena

Iguchi, Tadashi; Sugimoto, Jun; ; Okubo, Tsutomu; Murao, Yoshio

JAERI-M 91-173, 94 Pages, 1991/10

JAERI-M-91-173.pdf:2.01MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF-III test S3-3, S3-4 and S3-5; Counter current flow limitation phenomena in full radius core

Iguchi, Tadashi; *; Iwamura, Takamichi; ; Okubo, Tsutomu; Onuki, Akira; *; Murao, Yoshio

JAERI-M 91-172, 154 Pages, 1991/10

JAERI-M-91-172.pdf:3.19MB

no abstracts in English

JAEA Reports

Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in SCTF core-I forced feed tests

Iwamura, Takamichi; *; Sudo, Yukio; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; *; Murao, Yoshio

JAERI-M 91-093, 89 Pages, 1991/06

JAERI-M-91-093.pdf:1.87MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-II test S2-19; Quantitative evaluation of relation between degree of heat transfer enhancement due to radial power distribution and amount of increase of upward liquid flow rate during reflood in PWR-LOCA

Onuki, Akira; *; Iwamura, Takamichi; Iguchi, Tadashi; Abe, Yutaka; Murao, Yoshio

JAERI-M 91-033, 68 Pages, 1991/03

JAERI-M-91-033.pdf:1.4MB

no abstracts in English

Journal Articles

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

JAEA Reports

Comparison of facility characteristics between SCTF core-I and core-II

*; Iwamura, Takamichi; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; Murao, Yoshio

JAERI-M 90-130, 77 Pages, 1990/08

JAERI-M-90-130.pdf:1.72MB

no abstracts in English

89 (Records 1-20 displayed on this page)