|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Microstructure Based Hardening Models for Alloys Irradiated with Charged Particles an in the ATR and BOR60 Reactors
||Takuya Yamamoto, Peter Wells, Emanuelle Marquis, Dhriti Bhattacharyya, Tarik Saleh, Stuart Maloy, G. Robert Odette
|On-Site Speaker (Planned)
Interpreting ion-irradiation experiments to extremely high dose requires a robust model to predict mechanical properties from the evolved microstructure. New microstructure based irradiation hardening (Δσy) prediction models are described for Fe-Cr alloys, tempered martensitic steels and Alloy 800H, based on neutron irradiations. The individual hardening feature contributions to the yield stress (σy), σj, based on a dispersed-barrier hardening model were appropriately super-positioned, including the effect of strong pre-existing obstacles (σu) to evaluate the net Δσy. PIE results for ATR-1 irradiated Fe-3 to 18%Cr model alloys were used to optimize the obstacle strength factors (α) for dislocation loops (αl), α’ precipitates (αα’) and solute clusters (αc). The fitted hardening model for T91 was calibrated using BOR-60 data to account for voids (αv) and well-developed G-phase precipitates (αp), and an optimized σu, that is typical of this type of steel. Alloy 800H required a lower αp for smaller and more numerous precipitates.
||Planned: Supplemental Proceedings volume