Abstract
Radiation-induced embrittlement of reactor pressure vessel (RPV) steels can potentially limit the operating life of nuclear power plants. Over extended exposure to radiation doses, these body-centered cubic (BCC) irons demonstrate irradiation damage. Here, we present a continuum dislocation density (CDD) crystal plasticity model to capture the interaction among dislocations and self-interstitial atom (SIA) loops in α-iron. We demonstrate the importance of modeling cross slip using a combined stochastic Monte Carlo approach and the role of slip system strength anisotropy in capturing stochastic cross slip interactions. Through these captured interactions, the CDD crystal plasticity model can capture both the stress response and the physical evolution of dislocations on different slip system planes. Single-crystal verification experiments are used to calibrate the CDD crystal plasticity model, and a set of simplified polycrystalline simulations demonstrates the model’s ability to capture the stress response from tensile experiments on α-iron.
| Original language | English |
|---|---|
| Article number | 011018 |
| Journal | Journal of Engineering Materials and Technology, Transactions of the ASME |
| Volume | 144 |
| Issue number | 1 |
| Early online date | Sep 15 2021 |
| DOIs | |
| State | Published - Jan 2022 |
Keywords
- constitutive relations
- microstructure property relationships
- plastic behavior
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