Stress Corrosion Behavior of Steam Generator Material Alloy 800 and Alloy 690

WU Lian-lian; ZHANG Le-fu; PAN Xiang-feng; LI Ming-xin

Corrosion & Protection > 2014 > 35(1): 47-51.

WU Lian-lian, ZHANG Le-fu, PAN Xiang-feng, LI Ming-xin. Stress Corrosion Behavior of Steam Generator Material Alloy 800 and Alloy 690[J]. Corrosion & Protection, 2014, 35(1): 47-51.

Citation:

WU Lian-lian, ZHANG Le-fu, PAN Xiang-feng, LI Ming-xin. Stress Corrosion Behavior of Steam Generator Material Alloy 800 and Alloy 690[J]. Corrosion & Protection, 2014, 35(1): 47-51.

Citation:

WU Lian-lian, ZHANG Le-fu, PAN Xiang-feng, LI Ming-xin. Stress Corrosion Behavior of Steam Generator Material Alloy 800 and Alloy 690[J]. Corrosion & Protection, 2014, 35(1): 47-51.

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Stress Corrosion Behavior of Steam Generator Material Alloy 800 and Alloy 690

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Received Date: March 24, 2013

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Abstract

SSRT (Slow Strain Rate Test) was used to study and compare the tensile properties of domestic and imported steam generator materials alloy 800 and alloy 690 in simulated PWR primary loop water environment. Together with SEM fracphotographs, SSRT were used to study the SCC resistance and behavior of alloy 800 and alloy 690. The results showed that alloy 800 was susceptible to SCC in PWR primary water, while alloy 690 exhibited very good corrosion resistance.
- primary loop water environment,
- SSRT,
- tensile property,
- SCC

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