| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
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| Presentation Title |
Mapping the Swelling Behavior of Pure Chromium as a Function of Stress & Damage through a Combination of Four-point Bending, Finite Element Analysis, and Ion Irradiation |
| Author(s) |
Rijul Chauhan, Yinyin Hong, Kenneth Cooper, Yongchang Li, Artur Santos Paixao, Lin Shao |
| On-Site Speaker (Planned) |
Rijul Chauhan |
| Abstract Scope |
Developments in nuclear fusion and fission reactors necessitate diverse, durable materials to withstand radiation, temperature, and stress. However, data on the effects of mechanical stress on radiation-induced void swelling is scarce. This study presents a method to systematically investigate this relationship using four-point bending, finite element analysis (FEA), and ion irradiation. A pure chromium sample, a leading candidate for accident-tolerant fuel coating, was subjected to micro four-point bending and irradiated with a 2 MeV proton beam at Texas A&M University. Ansys FEA modeled the stresses, accounting for creep relaxation. Post-radiation, focused ion beam prepared specimens from various stress and damage regions for transmission electron microscopy analysis. Void data, excluding surface and interstitially affected zones, established a relationship between stress, damage level, and void swelling. This method elegantly maps swelling as a function of stress and damage within a single experiment, offering valuable data to model stresses at the cladding-coating interface. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Modeling and Simulation |