|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 (Δσ<SUB>y</SUB>) 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 (σ<SUB>y</SUB>), σ<SUB>j</SUB>, based on a dispersed-barrier hardening model were appropriately super-positioned, including the effect of strong pre-existing obstacles (σ<SUB>u</SUB>) to evaluate the net Δσ<SUB>y</SUB>. 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 (α<SUB>l</SUB>), α’ precipitates (α<SUB>α’</SUB>) and solute clusters (α<SUB>c</SUB>). The fitted hardening model for T91 was calibrated using BOR-60 data to account for voids (α<SUB>v</SUB>) and well-developed G-phase precipitates (α<SUB>p</SUB>), and an optimized σ<SUB>u</SUB>, that is typical of this type of steel. Alloy 800H required a lower α<SUB>p</SUB> for smaller and more numerous precipitates.
||Planned: Supplemental Proceedings volume