| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
|
| Presentation Title |
Modeling Low-temperature Hydrided Zircaloy Cladding Failure Under a Reactivity-initiated Accident |
| Author(s) |
Katheren Nantes, Miaomiao Jin, Arthur Motta |
| On-Site Speaker (Planned) |
Miaomiao Jin |
| Abstract Scope |
A reactivity-initiated accident (RIA) caused by the loss of a control rod results in rapid fuel thermal expansion and pellet cladding mechanical interaction which may deform the Zircaloy cladding at relatively low temperatures, when hydrides are still present. The hydrides are known to embrittle Zircaloy cladding, and may cause it to fail earlier than predicted. To investigate the likelihood of low-temperature failures during an RIA, we utilize the fuel performance code BISON to simulate cladding deformation as a function of pulse/reactivity characteristics (energy deposition, pulse width, energy distribution of deposited energy) within the pellet at different burnups. The goal of the project is to develop a physically-based failure criterion that considers not only hydrogen concentration but also hydride distribution and the state of stress in the cladding imposed on the cladding. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Modeling and Simulation, Nuclear Materials, |