Abstract
High energy particle irradiation of structural polycrystalline materials usually produces irradiation hardening and embrittlement. The development of predictive capability for the influence of irradiation on mechanical behavior is very important in materials design for next-generation reactors. A multiscale approach was implemented in this work to predict irradiation hardening of iron based structural materials. In the microscale, dislocation dynamics models were used to predict the critical resolved shear stress from the evolution of local dislocation and defects. In the macroscale, a viscoplastic self-consistent model was applied to predict the irradiation hardening in samples with changes in texture. The effects of defect density and texture were investigated. Simulated evolution of yield strength with irradiation agrees well with the experimental data of irradiation strengthening of stainless steel 304L, 316L and T91. This multiscale modeling can provide a guidance tool in performance evaluation of structural materials for next-generation nuclear reactors.
Original language | English |
---|---|
Pages (from-to) | 2496-2501 |
Number of pages | 6 |
Journal | Computational Materials Science |
Volume | 50 |
Issue number | 8 |
DOIs | |
State | Published - Jun 2011 |
Externally published | Yes |
Funding
This work was funded by the US Department of Energy’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program at Pacific Northwest National Laboratory. PNNL is operated by Battelle Memorial Institute for the US Department of Energy under contract No. DE-AC05-76RL01830.
Funders | Funder number |
---|---|
U.S. Department of Energy | |
Battelle | DE-AC05-76RL01830 |
Pacific Northwest National Laboratory |
Keywords
- Defect density
- Irradiation hardening
- Multiscale modeling
- Polycrystalline materials
- Texture