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OHNUKI, Akira, AKIMOTO, Hajime, MURAO, Yoshio (1995) Applicability of REFLA/TRAC Code to a small-Beak LOCA of PWR. Journal of Nuclear Science and Technology, 32. 245-256 doi:10.1080/18811248.1995.9731701

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Reference TypeJournal (article/letter/editorial)
TitleApplicability of REFLA/TRAC Code to a small-Beak LOCA of PWR
JournalJournal of Nuclear Science and Technology
AuthorsOHNUKI, AkiraAuthor
AKIMOTO, HajimeAuthor
MURAO, YoshioAuthor
Year1995 (March)Volume32
PublisherInforma UK Limited
DOIdoi:10.1080/18811248.1995.9731701Search in ResearchGate
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Mindat Ref. ID10246864Long-form Identifiermindat:1:5:10246864:1
GUID0
Full ReferenceOHNUKI, Akira, AKIMOTO, Hajime, MURAO, Yoshio (1995) Applicability of REFLA/TRAC Code to a small-Beak LOCA of PWR. Journal of Nuclear Science and Technology, 32. 245-256 doi:10.1080/18811248.1995.9731701
Plain TextOHNUKI, Akira, AKIMOTO, Hajime, MURAO, Yoshio (1995) Applicability of REFLA/TRAC Code to a small-Beak LOCA of PWR. Journal of Nuclear Science and Technology, 32. 245-256 doi:10.1080/18811248.1995.9731701
In(n.d.) Journal of Nuclear Science and Technology Vol. 32. Informa UK Limited

See Also

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OHNUKI, Akira, AKIMOTO, Hajime, MURAO, Yoshio (1993) Applicability of Core Thermal-Hydraulic Models in REFLA Code to 17×17 Type Fuel Assembly of PWR. Journal of Nuclear Science and Technology, 30. 187-202 doi:10.1080/18811248.1993.9734470
AKIMOTO, Hajime, MURAO, Yoshio (1996) Application of Simplified Condensation Model to PWR LBLOCA Transient Analysis with TRAC-PF1 Code. Journal of Nuclear Science and Technology, 33. 290-297 doi:10.1080/18811248.1996.9731908
OHNUKI, Akira, AKIMOTO, Hajime, MURAO, Yoshio (1992) Development of Interfacial Friction Model for Two-Fluid Model Code against Countercurrent Gas-Liquid Flow Limitation in PWR Hot Leg. Journal of Nuclear Science and Technology, 29. 223-232 doi:10.1080/18811248.1992.9731517
AKIMOTO, Hajime, MURAO, Yoshio (1992) Development of Reflood Model for Two Fluid Model Code Based on Physical Models Used in REFLA Code. Journal of Nuclear Science and Technology, 29. 642-655 doi:10.1080/18811248.1992.9731577
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
OHNUKI, Akira, AKIMOTO, Hajime (1999) Numerical Investigation of Heat Transfer Enhancement Phenomenon during the Reflood Phase of PWR-LOCA. Journal of Nuclear Science and Technology, 36. 1021-1029 doi:10.1080/18811248.1999.9726294
IGUCHI, Tadashi, MURAO, Yoshio, AKIMOTO, Hajime (1987) Assessment of Core Radial Power Profile Effect Model for REFLA Code by Using CCTF Data. Journal of Nuclear Science and Technology, 24. 536-546 doi:10.1080/18811248.1987.9735844
MURAO, Yoshio, FUJIKI, Kazuo, AKIMOTO, Hajime (1985) Experimental Assessment of Evaluation Model for Safety Analysis on Reflood Phase of PWR-LOCA. Journal of Nuclear Science and Technology, 22. 890-902 doi:10.1080/18811248.1985.9735741
AKIMOTO, Hajime, IGUCHI, Tadashi, MURAO, Yoshio (1987) System Pressure Effect on System and Core Cooling Behavior during Reflood Phase of PWR LOCA. Journal of Nuclear Science and Technology, 24. 276-288 doi:10.1080/18811248.1987.9735804
MURAO, Yoshio, AKIMOTO, Hajime, SUDOH, Takashi, OKUBO, Tsutomu (1982) Experimental Study of System Behavior during Reflood Phase of PWR-LOCA Using CCTF. Journal of Nuclear Science and Technology, 19. 705-719 doi:10.1080/18811248.1982.9734205
AKIMOTO, Hajime, IGUCHI, Tadashi, MURAO, Yoshio (1988) Effect of Pressure Drop through Broken Cold Leg on Thermal Hydraulic Behavior during Reflood Phase of PWR-LOCA. Journal of Nuclear Science and Technology, 25. 45-55 doi:10.1080/18811248.1988.9733554
 
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