Funder
DOE-NEUP
Chinese Scholarship Foundation
University of California Berkeley
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference54 articles.
1. Oxidation products of INCONEL alloys 600 and 690 in pressurized water reactor environments and their role in intergranular stress corrosion cracking;Ferguson;Metall. Mater. Trans.,2006
2. F.N. Speller Award Lecture: stress corrosion cracking in pressurized water reactors—interpretation, modeling, and remedies;Scott;Corrosion,2000
3. 11 - electrochemical techniques for monitoring and controlling corrosion in water-cooled nuclear reactor systems;Macdonald,2012
4. Corrosion testing of INCONEL Alloy 690 for PWR steam generators;Crum;J. Mater. Energy Syst.,1982
5. Effect of water on mechanical properties and stress corrosion behavior of Alloy 600, Alloy 690, EN82H Welds, and EN52 Welds;Brown;Corrosion,1999