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Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals [electronic resource] / prepared by H.M. Chung, W.J. Shack.

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Bibliographic Details
Online Access:	Online Access Online Access
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 Electronic eBook
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.

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Call Number:	Y 3.N 88:25/6892
Y 3.N 88:25/6892	Available