Stress corrosion crack initiation of alloy 600 in PWR primary water
Abstract
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. Processes controlling the SCC initiation in mill-annealed alloy 600 are discussed.
- Authors:
-
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Publication Date:
- 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)
- OSTI Identifier:
- 1355456
- Alternate Identifier(s):
- OSTI ID: 1364392; OSTI ID: 1550512
- Report Number(s):
- PNNL-SA-123949
Journal ID: ISSN 0010-938X; PII: S0010938X1730104X
- Grant/Contract Number:
- AC05-76RL01830; AC0576RL01830
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Corrosion Science
- Additional Journal Information:
- Journal Volume: 123; Journal ID: ISSN 0010-938X
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; Alloy; Stress corrosion; Crack initiation; SEM
Citation Formats
Zhai, Ziqing, Toloczko, Mychailo B., Olszta, Matthew J., and Bruemmer, Stephen M. Stress corrosion crack initiation of alloy 600 in PWR primary water. United States: N. p., 2017.
Web. doi:10.1016/j.corsci.2017.04.013.
Zhai, Ziqing, Toloczko, Mychailo B., Olszta, Matthew J., & Bruemmer, Stephen M. Stress corrosion crack initiation of alloy 600 in PWR primary water. United States. https://doi.org/10.1016/j.corsci.2017.04.013
Zhai, Ziqing, Toloczko, Mychailo B., Olszta, Matthew J., and Bruemmer, Stephen M. Thu .
"Stress corrosion crack initiation of alloy 600 in PWR primary water". United States. https://doi.org/10.1016/j.corsci.2017.04.013. https://www.osti.gov/servlets/purl/1355456.
@article{osti_1355456,
title = {Stress corrosion crack initiation of alloy 600 in PWR primary water},
author = {Zhai, Ziqing and Toloczko, Mychailo B. and Olszta, Matthew J. and Bruemmer, Stephen M.},
abstractNote = {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. Processes controlling the SCC initiation in mill-annealed alloy 600 are discussed.},
doi = {10.1016/j.corsci.2017.04.013},
journal = {Corrosion Science},
number = ,
volume = 123,
place = {United States},
year = {2017},
month = {4}
}
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Works referencing / citing this record:
An Approach to Estimate SCC Growing Rate in Slow Strain Rate Tensile Test Based on EPFEM
journal, June 2019
- Wang, Shuai; Xue, He; Cui, Yinghao
- Advances in Materials Science and Engineering, Vol. 2019