| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Simulating the Effects of Neutron Irradiation on Zirconium Alloys: A Crystal Plasticity Finite Element Approach |
| Author(s) |
Omid Sedaghat, Hamidreza Abdolvand |
| On-Site Speaker (Planned) |
Omid Sedaghat |
| Abstract Scope |
α-zirconium, with hexagonal close packed (HCP) crystal structure, has been widely used in the core of various nuclear reactors due to its low neutron absorption cross section and good corrosion resistance. In a nuclear reactor, zirconium alloys are exposed to an intensive neutron flux resulting in a phenomenon known as irradiation damage, which affects the deformation mechanism of the alloy over the service time. In this study, a dislocation based non-local crystal plasticity finite element (CPFE) model is developed to simulate the effects of crystal anisotropy and polycrystal microstructure on the localized stresses that develop as a result of neutron irradiation. The development of localized stresses as a results of irradiation growth is studied. It is shown that the model is capable of simulating the effects of prior cold-work on the irradiation growth and the associated localized stress fields that develop at the vicinity of grain boundaries. |
| Proceedings Inclusion? |
Planned: |