Stress corrosion crack initiation of alloy 600 in PWR primary water

Journal Article · 27 April 2017 · Corrosion Science

DOI: https://doi.org/10.1016/j.corsci.2017.04.013 · OSTI ID:1355456

Zhai, Ziqing ^[1]; Toloczko, Mychailo B. ^[1]; Olszta, Matthew J. ^[1]; Bruemmer, Stephen M. ^[1]

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1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

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.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)
• Grant/Contract Number: AC05-76RL01830
• OSTI ID: 1355456
• Report Number(s): PNNL-SA--123949; PII: S0010938X1730104X
• Journal Information: Corrosion Science, Journal Name: Corrosion Science Vol. 123; ISSN 0010-938X
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English