Audit of small break LOCA guidelines.

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)

Sensitivity analyses of a hypothetical 6 inch break, LOCA in Ascó NPP using RELAP/MOD3.2 /
Published: (2010)

Inadvertent reduction in primary coolant inventory in boiling water reactors during shutdown and startup.
Published: (1984)

TRACE/RELAP5 comparative calculations for double-ended LBLOCA and SBO /
by: Legan, S.
Published: (2016)

Degraded ability to isolate the reactor coolant system from low-pressure coolant systems in BWRS.
Published: (1986)

Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 /
by: Choi, T. S.
Published: (1998)

Assessment of RELAP5/MOD3 with the SNUF test simulating hot leg break LOCA in the view of mass and energy release analysis /
by: Hong, S. Joon
Published: (2001)

Simulation of LOCA 6" and LOCA 2" transients in the RHR of a PWR under low power conditions using RELAP5/MOD3.2 /
by: Martorell, S.
Published: (2000)

RELAP5 and TRACE calculations of LOCA in PWR /
by: Prosek, Andrej
Published: (2017)

Asymmetric blowdown loads on PWR primary systems : resolution of generic task action plan A-2 /
by: Hosford, S. B. (Steve B.)
Published: (1981)

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

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

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

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

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

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

EB 80-04 analysis of a PWR main steam sine break with continued feedwater addition.
Published: (1980)

Analysis of small-break LOCA transients combined with complete loss-of-feedwater accidents for the South Texas Project plant using TRAC-PF1/MOD1 /
by: Guyot, Carole Chantal, 1964-
Published: (1987)

RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA /
by: Tietsch, W.
Published: (1999)

Potential for loss of post-LOCA recirculation capability due to insulation debris blockage.
Published: (1985)

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)

Potential for loss of post-LOCA recirculation capability due to insulation debris blockage.
Published: (1988)

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)

EPR medium break LOCA benchmarking exercise using RELAP5 and CATHARE / Sebastian Gurgacz [and five others].
by: Gurgacz, Sebastian
Published: (2015)

Review of LOFT large break experiments : OCED LOFT project /
by: Modro, S. M.
Published: (1989)

Loss of high head safety injection.
Published: (1992)

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

Aluminum chemistry in a prototypical post-loss-of-coolant-accident, pressurized-water-reactor containment environment /
Published: (2006)

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

Phenomena identification and ranking table evaluation of chemical effects associated with generic safety issue 191 /
Published: (2009)

Experimental measurements of pressure drop across sump screen debris beds in support of generic safety issue 191 /
Published: (2007)

Post-test examination results from integral, high-burnup, fueled LOCA tests at Studsvik Nuclear Laboratory /
by: Flanagan, Michelle E., et al.
Published: (2013)

Assessment of RELAP5/MOD2 cycle 36.04 with LOFT large break LOCE L2-3 /
by: Bang, Y. S. (Young Seok), et al.
Published: (1992)

Errors in main steam line break analyses for determining containment parameters.
Published: (1991)

Potential for loss of shutdown cooling while at low reactor coolant levels.
Published: (1990)