Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems
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
- University of North Texas United States
- University of North Texas United States
Design, Grain Boundaries, 36 Materials Science, Tolerance Radiation Damage, Segregation, Policy And Economy, Creep, Nuclear Energy, Compatibility, Corrosion, Metals, Grain Boundary, 29 Energy Planning, Radiations, Alloys, Radiation Damage, Stability
Design, Grain Boundaries, 36 Materials Science, Tolerance Radiation Damage, Segregation, Policy And Economy, Creep, Nuclear Energy, Compatibility, Corrosion, Metals, Grain Boundary, 29 Energy Planning, Radiations, Alloys, Radiation Damage, Stability
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