The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304L stainless steel in boiling water reactor environment-Reference-Cited by-同舟云学术

The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304L stainless steel in boiling water reactor environment

Published:2019-12 Issue: Volume:161 Page:108183
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Kuang Wenjun,Hesterberg Justin,Was Gary S.

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference35 articles.

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2. IGSCC of non-sensitized stainless steels in high temperature water;Andresen;J. Nucl. Mater.,2008

3. BWR Vessels and Internals Project, Crack Growth in High Fluence BWR Materials-phase 1: Crack Growth Rate Testing of Types 304L and 316L at Doses Ranging From 3.5 to 13 Dpa;Anders,2009

4. A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels;Chopra;J. Nucl. Mater.,2011

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