Analysis of stress corrosion cracking in alloy 718 following commercial reactor exposure
Abstract
Alloy 718 is generally considered a highly corrosion-resistant material but can still be susceptible to stress corrosion cracking (SCC). The combination of factors leading to SCC susceptibility in the alloy is not always clear enough. In this paper, alloy 718 leaf spring (LS) materials that suffered stress corrosion damage during two 24-month cycles in pressurized water reactor service, operated to >45 MWd/mtU burn-up, was investigated. Compared to archival samples fabricated through the same processing conditions, little microstructural and property changes occurred in the material with in-service irradiation, contrary to high dose rate laboratory-based experiments reported in literature. Though the lack of delta phase formation along grain boundaries would suggest a more SCC resistant microstructure, grain boundary cracking in the material was extensive. Crack propagation routes were explored through focused ion beam milling of specimens near the crack tip for transmission electron microscopy as well as in polished plan view and cross-sectional samples for electron backscatter diffraction analysis. It has been shown in this study that cracks propagated mainly along random high-angle grain boundaries, with the material around cracks displaying a high local density of dislocations. The slip lines were produced through the local deformation of the leaf spring material abovemore »
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- AREVA Inc., Lynchburg, VA (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Center for Nanophase Materials Sciences (CNMS)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1286846
- Alternate Identifier(s):
- OSTI ID: 1252268
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 466; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 22 GENERAL STUDIES OF NUCLEAR REACTORS; Alloy 718; Post-irradiation examination; Stress corrosion cracking
Citation Formats
Leonard, Keith J., Gussev, Maxim N., Stevens, Jacqueline N., and Busby, Jeremy T. Analysis of stress corrosion cracking in alloy 718 following commercial reactor exposure. United States: N. p., 2015.
Web. doi:10.1016/j.jnucmat.2015.08.039.
Leonard, Keith J., Gussev, Maxim N., Stevens, Jacqueline N., & Busby, Jeremy T. Analysis of stress corrosion cracking in alloy 718 following commercial reactor exposure. United States. https://doi.org/10.1016/j.jnucmat.2015.08.039
Leonard, Keith J., Gussev, Maxim N., Stevens, Jacqueline N., and Busby, Jeremy T. Mon .
"Analysis of stress corrosion cracking in alloy 718 following commercial reactor exposure". United States. https://doi.org/10.1016/j.jnucmat.2015.08.039. https://www.osti.gov/servlets/purl/1286846.
@article{osti_1286846,
title = {Analysis of stress corrosion cracking in alloy 718 following commercial reactor exposure},
author = {Leonard, Keith J. and Gussev, Maxim N. and Stevens, Jacqueline N. and Busby, Jeremy T.},
abstractNote = {Alloy 718 is generally considered a highly corrosion-resistant material but can still be susceptible to stress corrosion cracking (SCC). The combination of factors leading to SCC susceptibility in the alloy is not always clear enough. In this paper, alloy 718 leaf spring (LS) materials that suffered stress corrosion damage during two 24-month cycles in pressurized water reactor service, operated to >45 MWd/mtU burn-up, was investigated. Compared to archival samples fabricated through the same processing conditions, little microstructural and property changes occurred in the material with in-service irradiation, contrary to high dose rate laboratory-based experiments reported in literature. Though the lack of delta phase formation along grain boundaries would suggest a more SCC resistant microstructure, grain boundary cracking in the material was extensive. Crack propagation routes were explored through focused ion beam milling of specimens near the crack tip for transmission electron microscopy as well as in polished plan view and cross-sectional samples for electron backscatter diffraction analysis. It has been shown in this study that cracks propagated mainly along random high-angle grain boundaries, with the material around cracks displaying a high local density of dislocations. The slip lines were produced through the local deformation of the leaf spring material above their yield strength. Also, the cause for local SCC appears to be related to oxidation of both slip lines and grain boundaries, which under the high in-service stresses resulted in crack development in the material.},
doi = {10.1016/j.jnucmat.2015.08.039},
journal = {Journal of Nuclear Materials},
number = ,
volume = 466,
place = {United States},
year = {Mon Aug 24 00:00:00 EDT 2015},
month = {Mon Aug 24 00:00:00 EDT 2015}
}
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Works referencing / citing this record:
Completing the picture through correlative characterization
journal, June 2019
- Burnett, T. L.; Withers, P. J.
- Nature Materials, Vol. 18, Issue 10