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MURAO, Yoshio, ARAYA, Fumimasa, IWAMURA, Takamichi, OKUMURA, Keisuke (1995) A Concept of Passive Safety, Pressurized Water Reactor System with Inherent Matching Nature of Core Heat Generation and Heat Removal. Journal of Nuclear Science and Technology, 32. 855-867 doi:10.1080/18811248.1995.9731787

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Reference TypeJournal (article/letter/editorial)
TitleA Concept of Passive Safety, Pressurized Water Reactor System with Inherent Matching Nature of Core Heat Generation and Heat Removal
JournalJournal of Nuclear Science and Technology
AuthorsMURAO, YoshioAuthor
ARAYA, FumimasaAuthor
IWAMURA, TakamichiAuthor
OKUMURA, KeisukeAuthor
Year1995 (September)Volume32
PublisherInforma UK Limited
DOIdoi:10.1080/18811248.1995.9731787Search in ResearchGate
Generate Citation Formats
Mindat Ref. ID10246950Long-form Identifiermindat:1:5:10246950:1
GUID0
Full ReferenceMURAO, Yoshio, ARAYA, Fumimasa, IWAMURA, Takamichi, OKUMURA, Keisuke (1995) A Concept of Passive Safety, Pressurized Water Reactor System with Inherent Matching Nature of Core Heat Generation and Heat Removal. Journal of Nuclear Science and Technology, 32. 855-867 doi:10.1080/18811248.1995.9731787
Plain TextMURAO, Yoshio, ARAYA, Fumimasa, IWAMURA, Takamichi, OKUMURA, Keisuke (1995) A Concept of Passive Safety, Pressurized Water Reactor System with Inherent Matching Nature of Core Heat Generation and Heat Removal. Journal of Nuclear Science and Technology, 32. 855-867 doi:10.1080/18811248.1995.9731787
In(n.d.) Journal of Nuclear Science and Technology Vol. 32. Informa UK Limited

See Also

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ARAYA, Fumimasa, MURAO, Yoshio (1995) Possibility of a Pressurized Water Reactor Concept with Highly Inherent Heat Removal Following Capability. Journal of Nuclear Science and Technology, 32. 339-350 doi:10.1080/18811248.1995.9731714
ARAYA, Fumimasa, MURAO, Yoshio, IWAMURA, Takamichi (1995) Transient Analysis for Design of Primary Coolant Pump Adopted to JAERI Passive Safety Reactor JPSR. Journal of Nuclear Science and Technology, 32. 1039-1046 doi:10.1080/18811248.1995.9731812
IWAMURA, Takamichi, ARAYA, Fumimasa, MURAO, Yoshio (1996) Application of PSA Methodology to Design Improvement of JAERI Passive Safety Reactor (JPSR). Journal of Nuclear Science and Technology, 33. 316-326 doi:10.1080/18811248.1996.9731911
KUNII, Katsuhiko, IWAMURA, Takamichi, MURAO, Yoshio (1997) Evaluation on Driving Force of Natural Circulation in Downcomer for Passive Residual Heat Removal System in JAERI Passive Safety Reactor JPSR. Journal of Nuclear Science and Technology, 34. 21-29 doi:10.1080/18811248.1997.9732052
IWAMURA, Takamichi, WATANABE, Hironori, OKUBO, Tsutomu, ARAYA, Fumimasa, MURAO, Yoshio (1993) CHF Experiments under Steady-State and Transient Conditions for Tight Lattice Core with Non-Uniform Axial Power Distribution. Journal of Nuclear Science and Technology, 30. 413-424 doi:10.1080/18811248.1993.9734498
IWAMURA, Takamichi, IGUCHI, Tadashi, ADACHI, Hiromichi, MURAO, Yoshio (1989) Quantitative Evaluation of Heat Transfer Enhancement due to Radial Power Distribution during Reflood Phase of PWR-LOCA. Journal of Nuclear Science and Technology, 26. 428-440 doi:10.1080/18811248.1989.9734330
ARAYA, Fumimasa, IWAMURA, Takamichi, OKUBO, Tsutomu, AKIMOTO, Hajime, MURAO, Yoshio (1992) Feasibility Study of Double-Flat-Core Type HCPWR for Reactivity Initiated Accidents. Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 34 (8) 776-786 doi:10.3327/jaesj.34.776
IWAMURA, Takamichi, OKUBO, Tsutomu, MURAO, Yoshio, SUEMURA, Takayuki, HIRAGA, Fujio (1991) Evaluation of DNBR under Operational and Accident Conditions for Double-Flat-Core Type HCLWR. Journal of Nuclear Science and Technology, 28. 45-58 doi:10.1080/18811248.1991.9731320
FUJII, Tadashi, KATAOKA, Yoshiyuki, MURASE, Michio, SUMIDA, Isao (1995) Effect of a Divided Wetwell on Heat Removal Capability of the Water Wall Type Passive Containment Cooling System. Journal of Nuclear Science and Technology, 32. 18-29 doi:10.1080/18811248.1995.9731665
WATANABE, Norio, HIRANO, Masashi (1992) Analysis of Operating Experience Involving Loss of Decay Heat Removal during Reactor Shutdown in Pressurized Water Reactors. Journal of Nuclear Science and Technology, 29. 1212-1223 doi:10.1080/18811248.1992.9731657
AKIMOTO, Hajime, IGUCHI, Tadashi, MURAO, Yoshio (1984) Pressure Drop through Broken Cold Leg during Reflood Phase of Loss-of-Coolant Accident of Pressurized Water Reactor. Journal of Nuclear Science and Technology, 21. 450-465 doi:10.1080/18811248.1984.9731068
 
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