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

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

Bibliographic Details
Main Author: Chung, H. M
Corporate Authors: Argonne National Laboratory, U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research. Division of Engineering Technology
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:
Austenitic stainless steel > Stress corrosion
Light water reactors > Materials > Stress corrosion

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