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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

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Reference TypeJournal (article/letter/editorial)
TitleEvaluation of DNBR under Operational and Accident Conditions for Double-Flat-Core Type HCLWR
JournalJournal of Nuclear Science and Technology
AuthorsIWAMURA, TakamichiAuthor
OKUBO, TsutomuAuthor
MURAO, YoshioAuthor
SUEMURA, TakayukiAuthor
HIRAGA, FujioAuthor
Year1991 (January)Volume28
PublisherInforma UK Limited
DOIdoi:10.1080/18811248.1991.9731320Search in ResearchGate
Generate Citation Formats
Mindat Ref. ID10246048Long-form Identifiermindat:1:5:10246048:5
GUID0
Full ReferenceIWAMURA, 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
Plain TextIWAMURA, 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
In(n.d.) Journal of Nuclear Science and Technology Vol. 28. Informa UK Limited

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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
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
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
OKUBO, Tsutomu, MURAO, Yoshio (1985) Assessment of Core Thermo-Hydrodynamic Models of REFLA-1D Code with CCTF Data for Reflood Phase of PWR-LOCA. Journal of Nuclear Science and Technology, 22. 983-994 doi:10.1080/18811248.1985.9735754
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
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, 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
OKUBO, Tsutomu, MURAO, Yoshio (1982) Effects of ECC Water Injection Rate on Reflood Phase during LOCA. Journal of Nuclear Science and Technology, 19. 593-595 doi:10.1080/18811248.1982.9734187
IGUCHI, Tadashi, OKUBO, Tsutomu, MURAO, Yoshio (1988) Effect of Loop Seal on Reflood Phenomena in PWR. Journal of Nuclear Science and Technology, 25. 520-527 doi:10.1080/18811248.1988.9733624
OKUBO, Tsutomu, IGUCHI, Tadashi, MURAO, Yoshio (1994) Experimental Study on Difference in Reflood Core Heat Transfer among CCTF, FLECHT-SET and Predicted with FLECHT Correlation. Journal of Nuclear Science and Technology, 31. 839-849 doi:10.1080/18811248.1994.9735230
 
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