An assessment of the emergency core cooling systems rulemaking hearing : concluding statement - safety phase /

Post-Dryout Heat Transfer.
by: Hewitt, G. F.
Published: (2017)

Survey of nucleonic heat transfer research and development.
Published: (1971)

Alkali metal coolants. : Proceedings of the symposium ... /
Published: (1967)

Topics in two-phase heat transfer and flow : presented at the winter annual meeting of the American Society of Mechanical Engineers, San Francisco, California, December 10-15, 1978 /
Published: (1978)

Thermal safety margins in nuclear reactors
by: Anglart, Henryk
Published: (2024)

Flow blockage of cooling water to safety system components.
Published: (1988)

Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3 /
by: Dabrowski, M., et al.
Published: (2014)

Assessment of emergency core cooling system effectiveness for light water nuclear power reactors.
by: Finlayson, Fred C.
Published: (1975)

Reactor coolant and associated systems in nuclear power plants : a safety guide.
Published: (1986)

Degradation of shutdown cooling system performance.
Published: (1993)

Accident analysis for nuclear power plants with modular high temperature gas cooled reactors /
Published: (2008)

Transient two-phase flow : proceedings of the third CSNI specialist meeting /
Published: (1983)

Inadequate core cooling instrumentation system.
Published: (1982)

Loss of shutdown cooling during disassembly of high pressure safety injection system check valve.
Published: (1991)

Validation of SCALE for high temperature gas-cooled reactor analysis /
Published: (2012)

The high temperature gas-cooled reactor : an overview of safety issues /
by: Solomon, Kenneth A., 1947-
Published: (1980)

Computer codes for small-break loss-of-coolant accidents : a Nordic assessment : final report of the NKA project SAK-3 /
by: Rathmann, Ole
Published: (1985)

The technology for an ultrasafe reactor : hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, U.S. House of Representatives, ninety-ninth Congress, second session, September 17, 1986.
Published: (1987)

Inadequate flow of essential service water to room coolers and heat exchangers for engineered safety-feature systems.
Published: (1990)

Component cooling water system gas accumulation and other performance issues.
Published: (2011)

Regulatory effectiveness of unresolved safety issue (USI) A-45, "shutdown decay heat removal requirements" /
Published: (2003)

Knowledge base report on emergency core cooling sump performance in operating light water reactors /
by: Natesan, K. (Krishnamurti), 1942-
Published: (2014)

Loss of safety injection capability.
Published: (1986)

Prediction of thermal-hydraulic performance of gas-cooled fast breeder reactors /
Published: (1977)

Nuclear reactor safety heat transfer /
Published: (1981)

High temperature gas cooled reactor fuels and materials /
Published: (2010)

Partial bypass of shutdown cooling flow from the reactor vessel.
Published: (1996)

Managing gas accumulation in emergency core cooling, decay heat removal, and containment spray systems.
Published: (2008)

Potential overpressurization of the component cooling water system.
Published: (1989)

Post accident debris cooling : proceedings of the Fifth Post Accident Heat Removal Information Exchange Meeting, July 28-30, 1982, Nuclear Research Center Karlsruhe, Karlsruhe /
Published: (1983)

Nuclear reactor safety heat transfer : presented at the Winter Annual Meeting of the American Society of Mechanical Engineers, Atlanta, Georgia, November 27-December 2, 1977 /
Published: (1977)

Symposium on the Thermal and Hydraulic Aspects of Nuclear Reactor Safety : [summaries] : presented at the winter annual meeting of the American Society of Mechanical Engineers, Atlanta, Georgia, November 27-December 2, 1977 /
Published: (1977)

Isolation of reactor coolant system from low-pressure systems outside containment.
Published: (1984)

Decay heat management practices during refueling outages.
Published: (1995)

Degradation of residual heat removal (RHR) system.
Published: (1981)

Safety analysis of WWER-440 nuclear power plants : potential consequences of a large primary to secondary system leakage accident.
Published: (2009)