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Title: 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:
 [1];  [1];  [1];  [1]
  1. 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}
}

Journal Article:

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Cited by: 12 works
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Works referenced in this record:

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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
  • DOI: 10.1155/2019/5651890