Cover Image

RBHT reflood heat transfer experiments data and analysis /

Bibliographic Details
Corporate Author:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Other Authors:	Hochreiter, L. E.
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Rgulatory Research, [2012]
Subjects:	Nuclear fuel rods > Experiments. Heat-transfer media > Experiments. Pressurized water reactors > Loss of coolant > Computer simulation. Nuclear power plants > Safety measures.
Online Access:	https://purl.fdlp.gov/GPO/gpo32435

Similar Items

TRACE assessment for effect of spacer grid in RBHT reflood heat transfer experiments /
by: Byung-Gilm, Huh, et al.
Published: (2018)

Rod bundle heat transfer test facility description /
Published: (2010)

Rod bundle heat transfer test facility test plan and design /
Published: (2010)

Rod bundle heat transfer facility two-phase mixture level swell and uncovery test experiments data report /
by: Hochreiter, L. E.
Published: (2016)

Rod bundle heat transfer facility steam cooling with droplet injection experiments data report /
by: Hochreiter, L. E.
Published: (2015)

Evaluation of the French Haut Taux de Combustion (HTC) critical experiment data /
by: Mueller, D. E.
Published: (2008)

Fuel fragmentation, relocation, and dispersal during the loss-of-coolant accident /
by: Raynaud, Patrick A. C.
Published: (2012)

RELAP/MOD2 calculations of OECD-LOFT test LP-SB-01 /
by: Hall, P. C. (Peter C.), et al.
Published: (1990)

RELAP5/MOD2 calculation of OECD-LOFT test LP-SB-03 /
by: Harwood, C., et al.
Published: (1990)

RELAP5/MOD2 calculations of OECD LOFT test LP-SB-2 /
by: Hall, P. C. (Peter C.)
Published: (1990)

Assessment of RELAP5/MOD2, cycle 36.04 using LOFT large break experiment L2-5 /
by: Bang, Seok Young, et al.
Published: (1990)

Assessment of RELAP5/MOD2 cycle 36.04 using LOFT intermediate break experiment L5-1 /
by: Lee, E. J., et al.
Published: (1992)

Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA /
by: Shih, Chunkuan
Published: (2016)

TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 /
by: Allen, E. J.
Published: (1990)

TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3 /
by: Allen, E. J.
Published: (1990)

TRAC-PF1/MOD1 post-test calculations of the OECD loft experiment LP-SB-2 /
by: Pelayo, F.
Published: (1990)

TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3 /
by: Allen, E. J., et al.
Published: (1990)

TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 /
by: Allen, E. J.
Published: (1990)

Analysis of LOFT test L5-1 using RELAP5/MOD2 /
by: Cooper, S.
Published: (1993)

Heat transfer processes during intermediate and large break loss-of-coolant accidents (LOCAs) /
by: Vojtek, I.
Published: (1986)

Evaluation of TRACE spacer grid model with FLECHT-SEASET reflood test /
by: Byung-Gil, Huh, et al.
Published: (2017)

Improvement of RELAP5/MOD3.3 reflood model based on the assessments against FLECHT-SEASET tests /
Published: (2011)

Influence of the wetting state of a heated surface on heat transfer and pressure loss in an evaporator tube /
by: Kohler, W., et al.
Published: (1986)

Developmental assessment of RELAP5/MOD3.1 with separate-effect and integral test experiments : model changes and options /
by: Analytis, G. Th. (Gerassimos Th.)
Published: (1998)

Loss of decay heat removal--10 CFR 50.54(f).
Published: (1988)

Investigations of the VVER-1000 Coolant Transient Benchmark Phase 1 with the coupled code system RELAP5/PARCS /
Published: (2009)

Loss of residual heat removal (RHR) while the reactor coolant system (RCS) is partially filled.
Published: (1987)

Loss of reactor coolant inventory and associated potential for loss of emergency mitigation functions while in a shutdown condition.
Published: (1998)

Potential for degradation of the emergency core cooling system and the containment spray system after a loss-of-coolant accident because of construction and protective coating deficiencies and foreign material in containment.
Published: (1998)

Result of BETHSY test 9.1.b using RELAP5/MOD3 /
by: Petelin, S.
Published: (1998)

Assessment of RELAP5/MOD2 against ECN-reflood experiments /
by: Woudstra, A., et al.
Published: (1993)

Reporting of errors and changes in large-break loss-of-coolant accident evaluation models of fuel vendors and compliance with 10 CFR 50.46(a)(3).
Published: (1997)

RELAP5/MOD2 analysis of LOFT experiment L9-4 /
by: Keevill, M. B.
Published: (1992)

Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility /
by: Kynčl, M., et al.
Published: (2013)

Summary of meeting held on October 12, 1979 to discuss responses to IE bulletins 79-05C and 79-06C and HPI termination criteria.
Published: (1979)

Depressurization of reactor coolant systems in pressurized-water reactors.
Published: (1987)

Inter-system discharge of reactor coolant.
Published: (1990)

Unanalyzed post-LOCA release paths.
Published: (1986)

Possible sudden loss of RCS inventory during low coolant level operation.
Published: (1988)

Core exit temperature response during an SBLOCA event in the Ascó NPP /
by: Freixa, J., et al.
Published: (2018)