Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference34 articles.
1. Alloy optimization for PWR steam generator heat-transfer tubing;Harrod;JOM,2001
2. G. L. Webb, M. G. Burke, Stress corrosion cracking behavior of Alloy 600 in high–temperature water, Proceedings of the 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, August 6-10, 1995, Breckenridge, CO, P. 41–55.
3. Effects of filler metal composition on joining properties of alloy 690 weldments;Kuo;Mat. Sci. Eng. A,2002
4. Structure, microsegregation and precipitates of an Alloy 690 ESR ingot in industrial scale;Wang;Met. Mat. Trans. A,2015
5. P.L. Andresen, M.M. Morra, A. Ahluwalia, J. Wilson, SCC of Alloy 690 and its weld metals, Proceedings of the 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2011, Colorado Springs, CO, P. 161–176.
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