Advanced Testing Techniques to Measure the PWSCC Resistance of Alloy 690 and its Weld Metals
Wrought Alloy 600 and its weld metals (Alloy 182 and Alloy 82) were originally used in pressurized water reactors (PWRs) due to the material's inherent resistance to general corrosion in a number of aggressive environments and because of a coefficient of thermal expansion that is very close to that of low alloy and carbon steel. Over the last thirty years, stress corrosion cracking in PWR primary water (PWSCC) has been observed in numerous Alloy 600 component items and associated welds, sometimes after relatively long incubation times. The occurrence of PWSCC has been responsible for significant downtime and replacement power costs. As part of an ongoing, comprehensive program involving utilities, reactor vendors and engineering/research organizations, this report will help to ensure that corrosion degradation of nickel-base alloys does not limit service life and that full benefit can be obtained from improved designs for both replacement components and new reactors.
- Research Organization:
- EPRI (US)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy, Science and Technology (NE) (US)
- DOE Contract Number:
- FC07-00NE22796
- OSTI ID:
- 837209
- Report Number(s):
- 1011202; TRN: US0701843
- Country of Publication:
- United States
- Language:
- English
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