Preliminary prediction of long-term aging and creep behavior of AM 316 SS
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
This report describes the development of initial mechanism models for the long term behavior of additively manufactured (AM), laser powder-bed fusion 316H stainless steel under the conditions expected in future advanced nuclear reactors. These models focus on key features of the material microstructure and response that differ from the conventionally-manufactured wrought material. Specifically, the report describes the development of models to capture the unique response of the AM material focusing on irradiation creep and swelling, the effect of internal stress, for example caused by dislocation structure, on precipitation, and the effect of the AM grain and dislocation structure on the macroscale creep and thermal aging behavior. This single mechanism models represent progress towards a complete, physics-based model for the long-term material behavior as well as elucidate key differences in the AM material behavior, when compared to the better-understood, conventionally-manufactured 316H.
- Research Organization:
- Argonne National Lab., Idaho Falls, ID (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- AC02-06CH11357; AC07-05ID14517; 89233218CNA000001
- OSTI ID:
- 2001071
- Report Number(s):
- ANL--AMMT-011; 185008
- Country of Publication:
- United States
- Language:
- English
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