A hierarchical methodology is introduced to predict the effects of radiation damage and irradiation conditions on the yield stress and internal stress heterogeneity developments in polycrystalline α-Fe. Simulations of defect accumulation under displacement cascade damage conditions are performed using spatially resolved stochastic cluster dynamics. The resulting void and dislocation loop concentrations and average sizes are then input into a crystal plasticity formulation that accounts for the change in critical resolved shear stress due to the presence of radiation induced defects. The simulated polycrystalline tensile tests show a good match to experimental hardening data over a wide range of irradiation doses. With this capability, stress heterogeneity development and the effect of dose rate on hardening is investigated. The model predicts increased hardening at higher dose rates for low total doses. By contrast, at doses above 10–2 dpa when cascade overlap becomes significant, the model does not predict significantly different hardening for different dose rates. In conclusion, the development of such a model enables simulation of radiation damage accumulation and associated hardening without relying on experimental data as an input under a wide range of irradiation conditions such as dose, dose rate, and temperature.
Dunn, Aaron, et al. "Multi-scale simulation of radiation damage accumulation and subsequent hardening in neutron-irradiated <i>α</i>-Fe." Modelling and Simulation in Materials Science and Engineering, vol. 24, no. 1, Nov. 2015. https://doi.org/10.1088/0965-0393/24/1/015005
Dunn, Aaron, Dingreville, Remi, & Capolungo, Laurent (2015). Multi-scale simulation of radiation damage accumulation and subsequent hardening in neutron-irradiated <i>α</i>-Fe. Modelling and Simulation in Materials Science and Engineering, 24(1). https://doi.org/10.1088/0965-0393/24/1/015005
Dunn, Aaron, Dingreville, Remi, and Capolungo, Laurent, "Multi-scale simulation of radiation damage accumulation and subsequent hardening in neutron-irradiated <i>α</i>-Fe," Modelling and Simulation in Materials Science and Engineering 24, no. 1 (2015), https://doi.org/10.1088/0965-0393/24/1/015005
@article{osti_1258477,
author = {Dunn, Aaron and Dingreville, Remi and Capolungo, Laurent},
title = {Multi-scale simulation of radiation damage accumulation and subsequent hardening in neutron-irradiated <i>α</i>-Fe},
annote = {A hierarchical methodology is introduced to predict the effects of radiation damage and irradiation conditions on the yield stress and internal stress heterogeneity developments in polycrystalline α-Fe. Simulations of defect accumulation under displacement cascade damage conditions are performed using spatially resolved stochastic cluster dynamics. The resulting void and dislocation loop concentrations and average sizes are then input into a crystal plasticity formulation that accounts for the change in critical resolved shear stress due to the presence of radiation induced defects. The simulated polycrystalline tensile tests show a good match to experimental hardening data over a wide range of irradiation doses. With this capability, stress heterogeneity development and the effect of dose rate on hardening is investigated. The model predicts increased hardening at higher dose rates for low total doses. By contrast, at doses above 10–2 dpa when cascade overlap becomes significant, the model does not predict significantly different hardening for different dose rates. In conclusion, the development of such a model enables simulation of radiation damage accumulation and associated hardening without relying on experimental data as an input under a wide range of irradiation conditions such as dose, dose rate, and temperature.},
doi = {10.1088/0965-0393/24/1/015005},
url = {https://www.osti.gov/biblio/1258477},
journal = {Modelling and Simulation in Materials Science and Engineering},
issn = {ISSN 0965-0393},
number = {1},
volume = {24},
place = {United States},
publisher = {IOP Publishing},
year = {2015},
month = {11}}
Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC04-94AL85000
OSTI ID:
1258477
Alternate ID(s):
OSTI ID: 1239006 OSTI ID: 22539245
Report Number(s):
SAND--2015-10308J; 642139
Journal Information:
Modelling and Simulation in Materials Science and Engineering, Journal Name: Modelling and Simulation in Materials Science and Engineering Journal Issue: 1 Vol. 24; ISSN 0965-0393
Measurement of Irradiation-enhanced Creep in Nuclear Materials: Proceedings of an International Conference Organized by the Commission of the European Communities at the Joint Research Centre, Petten, The Netherlands, May 5–6, 1976https://doi.org/10.1016/b978-0-7204-0572-9.50027-7