Stress corrosion crack initiation of alloy 600 in PWR primary water

doi:10.1016/j.corsci.2017.04.013

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:

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

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

Publication Date:: 2017-04-27

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.

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                    Zhai, Ziqing, Toloczko, Mychailo B., Olszta, Matthew J., & Bruemmer, Stephen M. Stress corrosion crack initiation of alloy 600 in PWR primary water.  United States.  doi:10.1016/j.corsci.2017.04.013.

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                    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.  doi:10.1016/j.corsci.2017.04.013.  https://www.osti.gov/servlets/purl/1355456.

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@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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DOI: 10.1016/j.corsci.2017.04.013

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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

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Stress corrosion crack initiation of alloy 600 in PWR primary water

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Stress corrosion crack (SCC) initiation of three mill-annealed (MA) 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 (IG) 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 IGSCC growth. Crack depth profiles were measured and related to DCPD-detected initiation response. Processes controlling the SCC initiation in MA alloy 600 are discussed. INmore »« less
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Title: Stress corrosion crack initiation of alloy 600 in PWR primary water

Abstract

Citation Formats

An Approach to Estimate SCC Growing Rate in Slow Strain Rate Tensile Test Based on EPFEM journal, June 2019

An Approach to Estimate SCC Growing Rate in Slow Strain Rate Tensile Test Based on EPFEM
journal, June 2019