Abstract
Destructive techniques to monitor nuclear reactor component health may not always be available during service, as they are time-consuming and often require pre-installed inspection coupons. Non-destructive evaluation (NDE) techniques can bridge this gap by rapidly identifying the state of mission-critical reactor components, via inference between NDE-measurable material properties and those of ultimate interest, such as ductility and toughness. Here, we demonstrate one such inference about the health of thermally aged cast austenitic stainless steels. Observations of surface acoustic wave peak (SAW) splitting correlate with spinodal decomposition-induced embrittlement as destructively measured by Charpy impact energy. Elastodynamic calculations and molecular dynamics simulations of the effects of spinodal decomposition on elastic moduli support that the new acoustic modes present are due to stiffening in the δ-ferrite domains. This discovery enables one to probe structure-property relationships in materials in a greatly accelerated manner, suggesting that similar inference methods can be used to determine material fitness-for-service, or to quickly uncover new structure-property relationships.
Original language | English |
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Article number | 118552 |
Journal | Acta Materialia |
Volume | 246 |
DOIs | |
State | Published - Mar 1 2023 |
Funding
The authors acknowledge generous financial support from the International Design Center (IDC) at the Massachusetts Institute of Technology (MIT) in collaboration with the Singapore University of Technology and Design (SUTD). M.P.S. acknowledges funding from the US Nuclear Regulatory Commission’s MIT Nuclear Education Faculty Development Program under Grant No. NRC-HQ-84-15-G-0045. S.A.A. acknowledges financial support from Raidah Saleem A. Al Baradie, Abdul Fattah Ahmed A. Al Dajani, the Strategic National Advancement (SNA) division at KAUST through the KAUST Gifted Student Program (KGSP) scholarship, as well as the Manson Benedict (1932) Fellowship from the Department of Nuclear Science and Engineering at MIT. C.A.D. acknowledges support through the INL Laboratory Directed Research & Development (LDRD) Program under DOE Idaho Operations Office Contract DE-AC07-05ID14517. This material is based upon work supported by the National Science Foundation Graduate Research Fellowship under Grant No. 1122374 and 174530. Any opinions, findings, and conclusions or recommendations expressed in this material are those of the author(s), do not necessarily reflect the views of the National Science Foundation.
Funders | Funder number |
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Department of Nuclear Science and Engineering | |
National Science Foundation | 1122374, 174530 |
U.S. Department of Energy | DE-AC07-05ID14517 |
U.S. Nuclear Regulatory Commission | NRC-HQ-84-15-G-0045 |
Massachusetts Institute of Technology | |
Laboratory Directed Research and Development | |
King Abdullah University of Science and Technology | |
Singapore University of Technology and Design | |
International Design Centre |
Keywords
- 304-type stainless steel
- 316-type stainless steel
- CF8
- CF8M
- Cast austenitic stainless steels (CASS)
- Non-destructive evaluation (NDE)
- Picosecond ultrasonics
- SAW Analysis
- Spinodal decomposition
- Stainless steel
- Surface acoustic wave (SAW)
- Thermal aging
- Thermal damage
- Transient grating spectroscopy (TGS)