Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems
The objective of this program is to improve the radiation tolerance of both austenitic and ferritic-martensitic (F-M) alloys projected for use in Generation IV systems. The expected materials limitations of Generation IV components include: creep strength, dimensional stability, and corrosion/stress corrosion compatibility. The material design strategies to be tested fall into three main categories: (1) engineering grain boundaries; (2) alloying, by adding oversized elements to the matrix; and (3) microstructural/nanostructural design, such as adding matrix precipitates. These three design strategies were tested across both austenitic and ferritic-martensitic alloy classes
- Research Organization:
- University of Wisconsin, Madison, WI; Univ. of Michigan, Ann Arbor, MI (United States); Idaho National Laboratory, Idaho Falls, ID; Pacific Northwest National Laboratory, Richland, WA; Japan Nuclear Energy Agency, O-Arai, Japan
- Sponsoring Organization:
- USDOE - Office of Nuclear Energy, Science and Technology (NE)
- DOE Contract Number:
- FG07-03ID14542
- OSTI ID:
- 861671
- Report Number(s):
- DOE/ID/14542-1; NERI 02-0110; TRN: US200710%%263
- Country of Publication:
- United States
- Language:
- English
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