NUREG-0737 technical specifications.

Technical resolution of Generic Issue No. B-59-(N-1) loop operation in BWRs and PWRs.
Published: (1986)

Transmittal of NUREG-0909 relative to the Ginna tube rupture.
Published: (1982)

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

Forwarding of 2 tables of appendix I, draft radiological effluent technical specifications, PWR, and NUREG-0133.
Published: (1978)

Circumferential cracking in the stainless steel pressurized heater sleeves of pressurized water reactors.
Published: (2006)

Development, implementation, and assessment of specific closure laws for inverted-annular film-boiling in a two-fluid model /
by: Cachard, François de
Published: (1996)

Standard technical specifications, General Electric BWR/6 plants.
Published: (2012)

Standard technical specifications, General Electric BWR/4 plants.
Published: (2012)

Coolant Chemistry Control and Effects on Fuel Reliability in Pressurized Heavy Water Reactors Report of a Technical Meeting.
by: IAEA
Published: (2021)

Standard technical specifications : General Electric Plants, BWR/4.
Published: (2004)

Standard technical specifications : General Electric Plants, BWR/6.
Published: (2004)

Post TMI requirements, NUREG-0737.
Published: (1980)

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

Resolution of generic issue 70, "Power-operated relief valve and block valve reliability," and generic issue 94, "Additional low-temperature overpressure protection for light-water reactors," pursuant to 10 CFR 50.54(f).
Published: (1990)

Water coolant technology of power reactors /
by: Cohen, P. (Paul)
Published: (1980)

Water coolant technology of power reactors.
by: Cohen, P. (Paul)
Published: (1969)

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

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

Experimental measurement of suppression pool void distribution during blowdown in support of Generic Issue 193 /
by: Ishii, M.
Published: (2014)

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

Supercritcal-water-cooled reactor [SCWR].
Published: (2007)

Systems summary of a Westinghouse pressurized water reactor nuclear power plant /
by: Masche, George
Published: (1971)

Implementation of NUREG-0313, technical report on material selection & processing GL for BWR coolant press boundary piping.
Published: (1981)

Analysis of the UPTF separate effects test 11 (steam-water countercurrent flow in the broken loop hot leg) using RELAP5/MOD2 /
by: Dillistone, M. J.
Published: (1992)

Pressurized Heavy Water Reactors : CANDU /
Published: (2022)

Pressurized Heavy Water Reactors : Atucha II /
Published: (2022)

Control rod drive (CRD) guide tube support pin failures at Westinghouse PWRS.
Published: (1982)

Reactor cavity annulus seal ring.
Published: (1978)

Inaccurate reactor water level indication and inadvertent draindown during shutdown.
Published: (1996)

New information regarding insulation material performance and debris blockage of PWR containment sumps.
Published: (1990)

Potential impact of debris blockage on emergency recirculation during design basis accidents at pressurized-water reactors.
Published: (2004)

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

Assessment study of RELAP5/MOD2, CYCLE 36.04 based on spray start-up test for DOEL-4 /
by: Moeyaert, P., et al.
Published: (1989)

Potential for loss of emergency cooling function due to a combination of operational and post-LOCA debris in containment.
Published: (1993)

Nuclear steam supply systems ; performance test codes.
Published: (1969)

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