Explore Books on
water cooled reactors
1-24 of 158 Books
TRAC-M programmer's guide
TRAC-M programmer's guide
By R. G. Steinke
Proceedings of the U.S. Nuclear Regulatory Commission
Proceedings of the U.S. Nuclear Regulatory Commission
By Water Reactor Safety Information Meeting (25th 1997 Bethesda, Md.)
TRAC-M validation test matrix
TRAC-M validation test matrix
By B. E. Boyack
The Department of Energy's water-cooled breeder program
The Department of Energy's water-cooled breeder program
By United States. General Accounting Office
TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
By P. Coddington
Assessment of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition
Assessment of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition
By K. W. Seul
Transactions of the Twenty-fifth Water Reactor Safety Information Meeting
Transactions of the Twenty-fifth Water Reactor Safety Information Meeting
By Water Reactor Safety Information Meeting (25th 1997 Bethesda, Md.)
Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))
Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))
By Iaea
Thermal-Hydraulics of Water Cooled Nuclear Reactors
Thermal-Hydraulics of Water Cooled Nuclear Reactors
By Francesco D'Auria
Drywell debris transport study
Drywell debris transport study
By D. V. Rao
Design Measure to Facilitate Implementation of Safeguards at Future Water Cooled (Technical Reports Series (International Atomic Energy Agency))
By International Atomic Energy Agency.
Water Chemistry of Nuclear Reactor Systems 6
By British Nuclear Energy Society
Water chemistry of nuclear reactor systems 2
By British Nuclear Energy Society
Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2
Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2
By L. Batet
Water chemistry of nuclear reactor systems
Water chemistry of nuclear reactor systems
By British Nuclear Energy Society
Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (9th 1999 Newport Beach, Calif.)
Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (8th 1997 Amelia Island, Fla.)
TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
By P Coddington
Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (3rd 1987 Traverse City, Mich.)
Water Chemistry of Nuclear Reactor Systems 3 (Water Chemistry of Nuclear Reactor Systems)
Water Chemistry of Nuclear Reactor Systems 3 (Water Chemistry of Nuclear Reactor Systems)
By International Conference Onw Ater Chemistry of Nuclear Reactor Systems
Guidebook on Destructive Examination of Water Reactor Fuel (Technical Reports Series (International Atomic Energy Agency))
Guidebook on Destructive Examination of Water Reactor Fuel (Technical Reports Series (International Atomic Energy Agency))
By International Atomic Energy Agency.
Preparation of radiological effluent technical specification for nuclear power plants
Preparation of radiological effluent technical specification for nuclear power plants
By United States. Office of Nuclear Reactor Regulation. Division of Site Safety and Environmental Analysis
Development of the LOFT prototype drag screen
Development of the LOFT prototype drag screen
By James R. Fincke