Pressure loadings of Soviet-designed VVER (Water-Cooled, Water-Moderated Energy Reactor) reactor release mitigation structures from large-break LOCAs

Pressure loadings of Soviet-designed VVER (Water-Cooled, Water-Moderated Energy Reactor) reactor release mitigation structures from large-break LOCAs [electronic resource]

Analyses have been carried out of the pressurization of the accident release mitigation structures of Soviet-designed VVER (Water-Cooled, Water-Moderated Energy Reactor) pressurized water reactors following large-break loss-of-coolant accidents. Specific VVER systems for which calculations were perf...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Office of Nuclear Energy, Science, and Technology ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1989.
Subjects:
Safety.
Hydraulics.
Water Moderated Reactors.
D Codes.
Reactor Safety.
Energy Transfer.
Mechanics.
Transients.
Containment.
Computer Codes.
Fluid Mechanics.
Reactor Accidents.
Energy Systems.
Pressurizing.
Cooling Systems.
Water Cooled Reactors.
Reactors.
R Codes.
Mitigation.
Heat Transfer.
Fission Product Release.
Loss Of Coolant.
Pwr Type Reactors.
Reactor Components.
Reactor Cooling Systems.
Accidents.
General Studies Of Nuclear Reactors.

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Call Number: E 1.99:conf-890855-51
E 1.99:conf-890855-51 Available

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