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Journal Articles

Applicability of REFLA/TRAC code to a small-break LOCA of PWR

Onuki, Akira; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 32(3), p.245 - 256, 1995/03

https://doi.org/10.3327/jnst.32.245
 Times Cited Count：1 Percentile：17.53(Nuclear Science & Technology)

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

JAEA Reports

Assessment of predictive capability of REFLA/TRAC code for large break LOCA transient in PWR using LOFT L2-5 test data

; Onuki, Akira; Murao, Yoshio

JAERI-M 94-037, 66 Pages, 1994/03

JAERI-M-94-037.pdf:1.64MB

no abstracts in English

JAEA Reports

Development of REFLA/TRAC code for engineering work station

Onuki, Akira; ; Murao, Yoshio

JAERI-M 94-026, 60 Pages, 1994/03

JAERI-M-94-026.pdf:1.81MB

no abstracts in English

JAEA Reports

Assessment of one dimensional reflood model in REFLA/TRAC code

; Onuki, Akira; Murao, Yoshio

JAERI-M 93-240, 83 Pages, 1993/12

JAERI-M-93-240.pdf:1.94MB

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

Assessment of TRAC-PF1/MOD1 code for large break LOCA in PWR

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

JAERI-M 93-028, 252 Pages, 1993/03

JAERI-M-93-028.pdf:5.98MB

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

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

JAEA Reports

Accident simulation tests for high conversion light water reactor using a high pressure water loop

Iwamura, Takamichi; Watanabe, Hironori; Araya, Fumimasa; Okubo, Tsutomu; Murao, Yoshio

JAERI-M 92-050, 46 Pages, 1992/03

JAERI-M-92-050.pdf:1.24MB

no abstracts in English

JAEA Reports

Evaluation of mechanistic DNB models using HCLWR CHF data

Iwamura, Takamichi; Watanabe, Hironori; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio

JAERI-M 92-033, 66 Pages, 1992/03

JAERI-M-92-033.pdf:1.37MB

no abstracts in English

Journal Articles

Application of subchannel code to DNB analysis of HCLWR

Iwamura, Takamichi; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio

Subchannel Analysis in Nuclear Reactors, p.281 - 301, 1992/00

no abstracts in English

JAEA Reports

Analysis of SCTF/CCTF counterpart test results

Okubo, Tsutomu; Sobajima, Makoto; Iwamura, Takamichi; Onuki, Akira; Abe, Yutaka; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-083, 155 Pages, 1990/06

JAERI-M-90-083.pdf:3.6MB

no abstracts in English

Journal Articles

Effect of liquid flow rate on film boiling heat transfer during reflood in rod bundle

Onuki, Akira; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 27(6), p.535 - 546, 1990/06

https://doi.org/10.3327/jnst.27.535

no abstracts in English

Journal Articles

Multi-dimensional thermal-hydraulics in pressure vessel during reflood phase of a PWR-LOCA

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

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.54 - 59, 1989/10

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

62 (Records 1-20 displayed on this page)