Stress corrosion crack initiation of alloy 600 in PWR primary water
Stress corrosion crack (SCC) initiation of three mill-annealed alloy 600 heats in simulated pressurized water reactor primary water has been investigated using constant load tests equipped with in-situ direct current potential drop (DCPD) measurement capabilities. SCC initiation times were greatly reduced by a small amount of cold work. Shallow intergranular attack and/or cracks were found on most high-energy grain boundaries intersecting the surface with only a small fraction evolving into larger cracks and intergranular SCC growth. Crack depth profiles were measured and related to DCPD-detected initiation response. Lastly, we discuss processes controlling the SCC initiation in mill-annealed alloy 600.
- Publication Date:
- Report Number(s):
- PNNL-SA-123949
Journal ID: ISSN 0010-938X; PII: S0010938X1730104X
- Grant/Contract Number:
- AC05-76RL01830; AC0576RL01830
- Type:
- Accepted Manuscript
- Journal Name:
- Corrosion Science
- Additional Journal Information:
- Journal Volume: 123; Journal ID: ISSN 0010-938X
- Publisher:
- Elsevier
- Research Org:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Org:
- USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; Alloy; Stress corrosion; Crack initiation; SEM
- OSTI Identifier:
- 1355456
- Alternate Identifier(s):
- OSTI ID: 1364392
- Free Publicly Accessible Full Text
-
Accepted Manuscript (DOE)
- Publisher's Version of Record
- https://doi.org/10.1016/j.corsci.2017.04.013