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Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals /

Bibliographic Details
Main Author: Chung, H. M.
Corporate Authors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, Argonne National Laboratory
Other Authors: Shack, W. J.
Format: Government Document Book
Language:English
Published: Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006.
Subjects:
Light water reactors > Materials > Stress corrosion.
Austenitic stainless steel > Stress corrosion.
Online Access:https://purl.fdlp.gov/GPO/LPS100255

Internet

https://purl.fdlp.gov/GPO/LPS100255

Available Online

Holdings details from Available Online
Call Number: Y 3.N 88:25/6892
 
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Y 3.N 88:25/6892 Available