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Title: Grain boundary damage evolution and SCC initiation of cold-worked alloy 690 in simulated PWR primary water

Abstract

Long-term grain boundary (GB) damage evolution and stress corrosion crack initiation in alloy 690 are being investigated by constant load tensile testing in high-temperature, simulated PWR primary water. Six commercial alloy 690 heats are being tested in various cold work conditions loaded at their yield stress. This paper reviews the basic test approach and detailed characterizations performed on selected specimens after an exposure time of ~1 year. Intergranular crack nucleation was observed under constant stress in certain highly cold-worked (CW) alloy 690 heats and was found to be associated with the formation of GB cavities. Somewhat surprisingly, the heats most susceptible to cavity formation and crack nucleation were thermally treated materials with most uniform coverage of small GB carbides. Microstructure, % cold work and applied stress comparisons are made among the alloy 690 heats to better understand the factors influencing GB cavity formation and crack initiation.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Pacific Northwest National Laboratory (PNNL), Richland, WA (US), Environmental Molecular Sciences Laboratory (EMSL)
Sponsoring Org.:
USDOE
OSTI Identifier:
1440691
Report Number(s):
PNNL-SA-129136
49618; 830403000
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Conference
Resource Relation:
Conference: Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (EDM 2017), 457-483
Country of Publication:
United States
Language:
English
Subject:
Alloy 690; PWSCC; creep cavity; crack initiation; grain boundary carbide; cold work; Environmental Molecular Sciences Laboratory

Citation Formats

Zhai, Ziqing, Toloczko, Mychailo B., Kruska, Karen, Schreiber, Daniel K., and Bruemmer, Stephen M. Grain boundary damage evolution and SCC initiation of cold-worked alloy 690 in simulated PWR primary water. United States: N. p., 2017. Web. doi:10.1007/978-3-319-67244-1_29.
Zhai, Ziqing, Toloczko, Mychailo B., Kruska, Karen, Schreiber, Daniel K., & Bruemmer, Stephen M. Grain boundary damage evolution and SCC initiation of cold-worked alloy 690 in simulated PWR primary water. United States. doi:10.1007/978-3-319-67244-1_29.
Zhai, Ziqing, Toloczko, Mychailo B., Kruska, Karen, Schreiber, Daniel K., and Bruemmer, Stephen M. Sat . "Grain boundary damage evolution and SCC initiation of cold-worked alloy 690 in simulated PWR primary water". United States. doi:10.1007/978-3-319-67244-1_29.
@article{osti_1440691,
title = {Grain boundary damage evolution and SCC initiation of cold-worked alloy 690 in simulated PWR primary water},
author = {Zhai, Ziqing and Toloczko, Mychailo B. and Kruska, Karen and Schreiber, Daniel K. and Bruemmer, Stephen M.},
abstractNote = {Long-term grain boundary (GB) damage evolution and stress corrosion crack initiation in alloy 690 are being investigated by constant load tensile testing in high-temperature, simulated PWR primary water. Six commercial alloy 690 heats are being tested in various cold work conditions loaded at their yield stress. This paper reviews the basic test approach and detailed characterizations performed on selected specimens after an exposure time of ~1 year. Intergranular crack nucleation was observed under constant stress in certain highly cold-worked (CW) alloy 690 heats and was found to be associated with the formation of GB cavities. Somewhat surprisingly, the heats most susceptible to cavity formation and crack nucleation were thermally treated materials with most uniform coverage of small GB carbides. Microstructure, % cold work and applied stress comparisons are made among the alloy 690 heats to better understand the factors influencing GB cavity formation and crack initiation.},
doi = {10.1007/978-3-319-67244-1_29},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {10}
}

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Works referenced in this record:

Theory of the formation of lattice defects during plastic strain
journal, November 1955


Precursor Evolution and Stress Corrosion Cracking Initiation of Cold-Worked Alloy 690 in Simulated Pressurized Water Reactor Primary Water
journal, May 2017

  • Zhai, Ziqing; Toloczko, Mychailo; Kruska, Karen
  • CORROSION, Vol. 73, Issue 10
  • DOI: 10.5006/2470

Degradation of Alloy 690 After Relatively Short Times
journal, October 2016

  • Arioka, Koji; Staehle, Roger W.; Yamada, T.
  • CORROSION, Vol. 72, Issue 10
  • DOI: 10.5006/2107