An Evaluation of liquid metal leak detection methods for the Clinch River Breeder Reactor Plant

An Evaluation of liquid metal leak detection methods for the Clinch River Breeder Reactor Plant [electronic resource]

This report documents an independent review and evaluation of sodium leak detection methods described in the Clinch River Breeder Reactor Preliminary Safety Analysis Report. Only information in publicly available documents was used in making the assessments.

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Richland, Wash. : Oak Ridge, Tenn. : Pacific Northwest National Laboratory (U.S.) ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1977.
Subjects:
Leak Detectors.
Alkali Metals.
Breeder Reactors.
Epithermal Reactors.
Cooling Systems.
Metals.
Reactors.
Liquid Metal Cooled Reactors.
Testing.
Sodium Cooled Reactors.
Power Reactors.
Fbr Type Reactors.
Clinch River Breeder Reactor.
Fast Reactors.
Reactor Components.
Elements.
Leak Testing.
Reactor Cooling Systems.
Sodium.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:pnl-2447
E 1.99:pnl-2447 Available

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