Environmentally assisted cracking in light water reactors

Environmentally assisted cracking in light water reactors [electronic resource]

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This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from April 1995 to December 1995. Topics that have been investigated include fatigue of carbon and low-alloy steel used in reactor piping and pre...

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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. : U.S. Nuclear Regulatory Commission ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1996.
Subjects:
Pressure Vessels.
Reactor Materials.
Cracks.
Steel-astm-a302.
Austenitic Steels.
Bwr Type Reactors.
Inconel 690.
Low Alloy Steels.
Fatigue.
Ferritic Steels.
Carbon Steels.
Crack Propagation.
Steel-astm-a533.
Inconel 600.
Stainless Steel-304.
Steel-astm-a533-b.
Stress Corrosion.
Pipes.
Pwr Type Reactors.
Steel-astm-a106.
Materials Science.
Nuclear Power Reactors And Associated Plants.

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Call Number: E 1.99: anl--96/1-vol.21
E 1.99: anl--96/1-vol.21 Available

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