About this Abstract |
Meeting |
2021 TMS Annual Meeting & Exhibition
|
Symposium
|
Accelerated Discovery and Qualification of Nuclear Materials for Energy Applications
|
Presentation Title |
Improving Irradiation Resistance of Alloys by Controlling Defect Diffusion: A Modeling Perspective |
Author(s) |
Yongfeng Zhang, Miao Song, Xiang Liu, Lingfeng He, Daniel Schwen , Xiaoyuan Lou |
On-Site Speaker (Planned) |
Yongfeng Zhang |
Abstract Scope |
Irradiation damages materials by producing lattice defects and inducing undesirable component segregation/precipitation. The amount and the rate of damage accumulation depend critically on the diffusion of defects. Taking austenitic FeNiCr alloy as an example, the feasibility of improving the irradiation resistance of traditional alloys by minor alloying is studied using lattice kinetic Monte Carlo. It’s found that, additives that trap point defects can in general reduce radiation induced segregation (RIS) of Cr and void swelling. However, the strong trapping itself can cause RIS and precipitation of additives. As such, the mitigation effect disappears at high doses when the additive concentrations are low. In alloys with relatively high additive concentrations, the mitigation effect may be sustained at high doses due to the formation of high density of nanosized precipitates. The modeling findings are consistent with experimental observations in the literature and from recent proton irradiation experiments. |
Proceedings Inclusion? |
Planned: |