Mechanistic insights into lead-accelerated stress corrosion cracking of Alloy 600

Author:

Hur Do Haeng,Choi Won-Ik,Song Geun Dong,Jeon Soon-Hyeok,Lim Sangyeob

Funder

National Research Foundation of Korea (NRF)

Korea government

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference79 articles.

1. Pressurized Water Reactor Secondary Water Chemistry Guidelines - Revision 6;EPRI,2004

2. Pitting corrosion and its countermeasures for pressurized water reactor steam generator tubes;Hur;Corrosion,2006

3. Sulfur at crack tips in Alloy 600 service samples;Thomas,2005

4. Root causes of intergranular attack in an operating nuclear steam generator tube;Hur;J. Nucl. Mater.,2008

5. Secondary side corrosion of French PWR steam generator tubing: Contribution of surface analyses to the understanding of the degradation process;Boursier,1999

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