| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Development of a Plasticity Model for Non-Hydrided and Hydrided Beta-Treated Zircaloy-4 Based on the Results From Notched Tensile, Torsion and Compression Testing |
| Author(s) |
Brian V. Cockeram, James Sobotka |
| On-Site Speaker (Planned) |
Brian V. Cockeram |
| Abstract Scope |
The testing of notched tensile, tension-torsion, torsion, compression-torsion and compression specimens for non-hydrided and hydrided beta-treated Zircaloy-4 were performed to provide results over a range of stress-state defined by triaxiality and lode parameter. These data were used to develop a new plasticity law consists of yield surface defined using n-ellipses that distort with plastic deformation to accommodate the tension-compression asymmetry. Implementation of damage into the plasticity law is used to predict the displacement and strain to failure. The addition of hydrogen is shown to significantly reduce the strain to failure for notched specimens that have a more constrained stress state represented by a triaxiality values of 0.33 and higher. For stress-states under shear or compression at a triaxiality less than 0.2, hydrogen has less of an effect on the strain to failure. Implementation of the plasticity model and damage model provide insight into the deformation mechanisms. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Modeling and Simulation |