JOPSS - Search Results

JAEA Reports

Experimental result of BWR post-CHF tests; Critical heat flux and post-CHF heat transfer coefficient (Contract research)

Iguchi, Tadashi; Iwaki, Chikako*; Anoda, Yoshinari

JAERI-Research 2001-060, 91 Pages, 2002/02

JAERI-Research-2001-060.pdf:6.34MB

no abstracts in English

JAEA Reports

Data report of BWR post-CHF tests; Transient core thermal-hydraulic program (Contract research)

Iguchi, Tadashi; Ito, Hideo; Kiuchi, Toshio; Watanabe, Hironori; Kimura, Mamoru*; Anoda, Yoshinari

JAERI-Data/Code 2001-013, 502 Pages, 2001/03

JAERI-Data-Code-2001-013.pdf:32.38MB

no abstracts in English

JAEA Reports

Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA

Onuki, Akira; ; Iguchi, Tadashi; Murao, Yoshio

JAERI-Research 94-012, 59 Pages, 1994/08

JAERI-Research-94-012.pdf:1.75MB

no abstracts in English

Journal Articles

Applicability of core thermal-hydraulic models in REFLA code to 1717 type fuel assembly of PWR

Onuki, Akira; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 30(3), p.187 - 202, 1993/03

https://doi.org/10.3327/jnst.30.187

Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal-hydraulic model for reflooding phenomena in a PWR-LOCA

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

Proc. of the 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 1, p.723 - 732, 1993/00

no abstracts in English

JAEA Reports

Interaction between zircaloy tube and inconel spacer grid at high temperatures

Nagase, Fumihisa; ; Uetsuka, Hiroshi; Furuta, Teruo

JAERI-M 90-165, 35 Pages, 1990/09

JAERI-M-90-165.pdf:3.39MB

no abstracts in English

JAEA Reports

Report on Reflood Experiment of Grid Spacer Effect

; Murao, Yoshio

JAERI-M 84-131, 223 Pages, 1984/06

JAERI-M-84-131.pdf:4.14MB

no abstracts in English

Journal Articles

Effect of grid spacers on reflood heat transfer in PWR-LOCA

; Murao, Yoshio

Journal of Nuclear Science and Technology, 21(2), p.103 - 114, 1984/00

https://doi.org/10.3327/jnst.21.103

Times Cited Count：11 Percentile：73.2(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Preliminary Analysis of the Effect of the Grid Spacers on the Reflood Heat Transfer

; Murao, Yoshio

JAERI-M 9992, 41 Pages, 1982/02

JAERI-M-9992.pdf:1.03MB

no abstracts in English

Presentation/Publication Type

Journal/Book Title

Meeting title

First Author

Keyword

Language

Publication Year

Held year of conference

Experimental result of BWR post-CHF tests; Critical heat flux and post-CHF heat transfer coefficient (Contract research)

Data report of BWR post-CHF tests; Transient core thermal-hydraulic program (Contract research)

Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA

Applicability of core thermal-hydraulic models in REFLA code to 1717 type fuel assembly of PWR

Thermal-hydraulic model for reflooding phenomena in a PWR-LOCA

Interaction between zircaloy tube and inconel spacer grid at high temperatures

Report on Reflood Experiment of Grid Spacer Effect

Effect of grid spacers on reflood heat transfer in PWR-LOCA

Preliminary Analysis of the Effect of the Grid Spacers on the Reflood Heat Transfer