Multiple equipment failures in safety-related systems.

Westinghouse two-loop NSSS.
Published: (1979)

Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks /
by: Mueller, D. E.
Published: (2015)

BWR off-gas systems--enclosing NUREG/CR-0727.
Published: (1979)

LOFT system and test description (5.5-ft nuclear core 1 loces) /
by: Reeder, Douglas L.
Published: (1978)

Assessment study of RELAP5/MOD2 against 25 dryout experiments conducted at the Royal Institute of Technology /
by: Sjoberg, A., et al.
Published: (1986)

NRC staff review of responses to I&E Bulletin 79-08.
Published: (1979)

Referencing 6/29/79 letter re multiple equipment failures.
Published: (1979)

Evaluation of semi-scale small break experiment.
Published: (1979)

BWR control rod failures.
Published: (1980)

Relaxation of staff position in Generic Letter 83-28, Item 2.2 Part 2 "Vendor interface for safety-related components".
Published: (1990)

Guidebook to light water reactor safety analysis /
Published: (1985)

Thermal mixing tests in a semiannular downcomer with interacting flows from cold legs /
by: Tuomisto, H. (Harri), et al.
Published: (1986)

Assessment of RELAP5/MOD 2 against critical flow data from Marviken tests JIT 11 and CFT 21 /
by: Rosdahl, Ö. (Östen), et al.
Published: (1986)

Assessment of RELAP5/MOD 2 against Marviken jet impingement test 11 level swell /
by: Rosdahl, Ö. (Östen), et al.
Published: (1986)

Transmitting regulatory guide 2.6 for comment.
Published: (1979)

2D/3D Program work summary report /
Published: (1993)

Super light water reactors and super fast reactors : supercritical-pressure light water cooled reactor /
Published: (2010)

Materials and water chemistry for supercritical water-cooled reactors /
Published: (2018)

Reactor safety study : an assessment of accident risks in U.S. commercial nuclear power plants : executive summary [and appendices].
Published: (1975)

Water cooled reactor safety : an assessment prepared for the Committee on Reactor Safety Technology.
Published: (1970)

Loss of flow analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP /
by: Shih, Chunkuan
Published: (2018)

Design, instrumentation, and testing of a steel containment vessel model /
by: Luk, V. K.
Published: (2000)

Final safety evaluation report related to certification of the AP1000 standard design : docket no. 52-006.
Published: (2004)

Final safety evaluation report related to certification of the AP1000 standard design : docket no. 52-006.
by: Quinones-Navarro, Lauren, et al.
Published: (2005)

Spatial effects and uncertainty analysis for rod ejection accidents in a PWR /
by: Avvakumov, A., et al.
Published: (2007)

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

Post-test analysis of Hot Leg 2x25% break at PSB-VVER facility using TRACE V5.0 code /
by: Heralecky, P.
Published: (2011)

Modifications to boiling water reactor control rod drive systems.
Published: (1980)

Mark II generic acceptance criteria for lead plants.
Published: (1978)

Issuance of NUREG-0313, rev 1, "Technical report on material selection and processing guidelines for BWR coolant pressure".
Published: (1980)

Failure of control rod drive mechanism lead screw male coupling at a Babcock and Wilcox-designed facility.
Published: (2007)

Final safety evaluation report related to certification of the AP1000 standard plant design : supplement 2.
Published: (2011)

IEB 80-07 BWR jet pump assembly failure.
Published: (1980)

Assessment and management of ageing of major nuclear power plant components important to safety : PWR pressure vessels, 2007 update.
Published: (2007)

Post-test calculation of the ROSA-2 test 3 using RELAP5/MOD3.3 /
by: Martinez-Quiroga, Victor, et al.
Published: (2019)

Assessment of TRACE 5.0 against ROSA-2 test 3 countertest to PKL /
by: Gallardo, S.
Published: (2019)