|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Computational Materials Science and Engineering for Nuclear Energy
||Computer Simulations of Dislocation-obstacle Interactions in the Hardening and Recovery of BWR-irradiated 304L SS
||Justin Hesterberg, Jesse J Carter, Denise Paraventi, Richard W Smith, Gary S Was
|On-Site Speaker (Planned)
Susceptibility to irradiation-assisted stress corrosion cracking has been previously linked to localized deformation, but a mechanistic description sufficient to guide the development of mitigation strategies does not yet exist. The relation is made particularly complex by the formation of multiple types of irradiation-induced defects, including dislocation loops and solute clusters, each having their own evolutionary kinetics and specific interactions with mobile dislocations, but also at times being spatially linked. In support of mechanical tests following post-irradiation annealing of BWR-irradiated 304L SS, computational models of dislocation-obstacle interactions have been applied at the mesoscopic and atomistic length scales. The purpose of the work is to develop a hardening model in which the superposition of barrier strengths results from an explicit spatial correlation between interstitial loops and solute clusters enriched by either Ni-Si or Cu-Al, as measured previously by TEM/APT following various PIA treatments.
||Planned: Supplemental Proceedings volume