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)

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

BWR control rod failures.
Published: (1980)

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

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

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

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

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)

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)

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

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

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

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

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

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

Clarification of the term "operable" as it applies to single failure criterion for safety systems required by TS.
Published: (1980)

Keeping the space environment safe for civil and commercial users hearing before the Subcommittee on Space and Aeronautics, Committee on Science and Technology, House of Representatives, One Hundred Eleventh Congress, first session, April 28, 2009.
Published: (2009)

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

Drywell debris transport study : final report.
Published: (1999)

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

Simulation of ROSA-2 test-2 experiment : application to nuclear power plant /
by: Gallardo, S.
Published: (2019)

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

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

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

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

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

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