Clinch River Breeder Reactor Plant hot leg pipe evaluation. Supplement to the primary pipe integrity status report.

Clinch River Breeder Reactor Plant [electronic resource] : hot leg pipe evaluation. Supplement to the primary pipe integrity status report.

Postulated large breaks in the primary hot-leg piping had been analyzed and the results show that no loss of core coolable geometry would occur. Further study has been performed, particularly in ascertaining the upper bounds of the consequence of such a postulated break. This was done both in terms...

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Bibliographic Details
Online Access: Full Text (via OSTI)
Corporate Author: Westinghouse Electric Corporation (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1985.
Subjects:
Clinch River Breeder Reactor.
Primary Coolant Circuits.
Loss Of Coolant.
Transients.
Cracks.
Leaks.
Pipes.
Corrosion.
Ruptures.
Stress Analysis.
Fatigue.
Reliability.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:ward-d--0137
E 1.99:ward-d--0137 Available

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