SCC testing of nuclear steam generator tubing materials

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作者：
Babcock and Wilcox International Division, United States [1 ]
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来源：
JOM | / 5卷 / 39-41期
关键词：
Alloys - Chemistry - Corrosion - Heat exchangers - Manufacture - Metallographic microstructure - Nuclear reactors - Steam generators - Stress corrosion cracking - Tubes (components);
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摘要：
The integrity of heat-exchanger tubes in a nuclear reaction system is crucial for the safe operation of a power plant. In order to study the corrosion behavior of certain alloys, constant extension rate (CERT) tests were performed on alloy 690 and alloy 800 nuclear steam generator tubing specimens. In this article, the CERT test results (such as maximum stress achieved and crack morphology) are correlated to tubing microstructure, chemistry, and manufacturing processes.
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