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JAEA Reports

Reactor safety issues resolved by 2D/3D program

JAERI 1336, 362 Pages, 1995/09

JAERI-1336.pdf:15.72MB

no abstracts in English

JAEA Reports

2D/3D program work summary report

JAERI 1335, 376 Pages, 1995/09

JAERI-1335.pdf:16.12MB

no abstracts in English

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

Journal Articles

Assessment of predictive capability of REFLA/TRAC code for peak clad temperature during reflood in LBLOCA of PWR with small scale test, SCTF and CCTF data

; Onuki, Akira; Murao, Yoshio

Validation of Systems Transients Analysis Codes (FED-Vol. 223), 0, 8 Pages, 1995/00

no abstracts in English

Journal Articles

Experimental study on difference in reflood core heat transfer among CCTF, FLECHT-SET and predicted with FLECHT correlation

Okubo, Tsutomu; Iguchi, Tadashi; Murao, Yoshio

Journal of Nuclear Science and Technology, 31(8), p.839 - 849, 1994/08

https://doi.org/10.3327/jnst.31.839
 Times Cited Count：1 Percentile：26.96(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-15(Run 75); Investigation of FLECHT-SET coupling test results

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

JAERI-M 91-227, 89 Pages, 1992/01

JAERI-M-91-227.pdf:1.82MB

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

Implementation of an implicit method into heat conduction calculation of TRAC-PF1/MOD2 code

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

JAERI-M 90-122, 36 Pages, 1990/08

JAERI-M-90-122.pdf:0.92MB

None

JAEA Reports

Evaluation report on SCTF core-III test S3-9; Investigation of CCTF coupling test results under an evaluation model condition in PWRs with cold-leg-injection-type ECCS

Okubo, Tsutomu; Iguchi, Tadashi; Iwamura, Takamichi; ; Onuki, Akira; Abe, Yutaka; *; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-046, 114 Pages, 1990/03

JAERI-M-90-046.pdf:2.26MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-III test S3-17; Investigation of thermo-hydrodynamic behavior during reflood phase of LOCA in a PWR with vent valves

Okubo, Tsutomu; Iguchi, Tadashi; Iwamura, Takamichi; ; Onuki, Akira; Abe, Yutaka; *; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-036, 120 Pages, 1990/03

JAERI-M-90-036.pdf:2.49MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-III tests S3-7 and S3-8; Investigation of tie plate water temperature distribution effects on water break-through and core cooling during reflooding in PWRs with combined-injection-type ECCS

Okubo, Tsutomu; Iguchi, Tadashi; Iwamura, Takamichi; ; Onuki, Akira; Abe, Yutaka; *; *; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-035, 143 Pages, 1990/03

JAERI-M-90-035.pdf:3.07MB

no abstracts in English

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-AA2(Run 58); Investigation of downcomer injection effects

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

JAERI-M 89-227, 96 Pages, 1990/01

JAERI-M-89-227.pdf:2.12MB

no abstracts in English

Journal Articles

Application of REFLA core model to safety evaluation code

*; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 25(2), p.190 - 197, 1988/02

https://doi.org/10.3327/jnst.25.190

no abstracts in English

Journal Articles

Effect of pressure drop through broken cold leg on thermal hydraulic behavior during reflood phase of PWR-LOCA

; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 25(1), p.45 - 55, 1988/01

https://doi.org/10.3327/jnst.25.45

no abstracts in English

Journal Articles

Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data

; Murao, Yoshio; ; ; ; *

Journal of Nuclear Science and Technology, 24(11), p.887 - 896, 1987/11

https://doi.org/10.3327/jnst.24.887
 Times Cited Count：2 Percentile：29.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effect of decay heat level on reflood phenomena during PWR-LOCA

; Murao, Yoshio

Journal of Nuclear Science and Technology, 24(10), p.821 - 831, 1987/10

https://doi.org/10.3327/jnst.24.821
 Times Cited Count：1 Percentile：19.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Assessment of core radial power profile effect model of REFLA code by using CCTF data

; Murao, Yoshio;

Journal of Nuclear Science and Technology, 24(7), p.536 - 546, 1987/07

https://doi.org/10.3327/jnst.24.536
 Times Cited Count：3 Percentile：38.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of initial downcomer water accumulation velocity effects on reflood phase of PWR-LOCA

; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 24(7), p.573 - 579, 1987/07

https://doi.org/10.3327/jnst.24.573
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

System pressure effect on system and core cooling behavior during reflood phase of PWRLOCA

; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 24(4), p.276 - 288, 1987/04

https://doi.org/10.3327/jnst.24.276
 Times Cited Count：3 Percentile：38.12(Nuclear Science & Technology)

no abstracts in English

40 (Records 1-20 displayed on this page)