Primary pipe rupture accident analysis for the Clinch River Breeder Reactor

Primary pipe rupture accident analysis for the Clinch River Breeder Reactor [electronic resource]

In this report, the thermal transient response of the CRBR to a severe primary coolant flow perturbation, initiated by a rupture of the primary heat transport system piping, is analyzed. This hypothetical accident is studied under the further assumption that the plant protection system does function...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Brookhaven National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Upton, N.Y. : Oak Ridge, Tenn. : Brookhaven National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1976.
Subjects:
Breeder Reactors.
Epithermal Reactors.
Primary Coolant Circuits.
Reactor Shutdown.
Reactor Protection Systems.
Cooling Systems.
Reactors.
Liquid Metal Cooled Reactors.
Sodium Cooled Reactors.
Power Reactors.
Fbr Type Reactors.
Fast Reactors.
Clinch River Breeder Reactor.
Pipes.
Failures.
Shutdowns.
Loss Of Coolant.
Scram.
Reactor Components.
Ruptures.
Reactor Cooling Systems.
Accidents.
Reactor Accidents.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:bnl-nureg-21656
E 1.99:bnl-nureg-21656 Available

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