| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Quantifying Zirconium Embrittlement Due to Hydride Microstructure Using Image Analysis |
| Author(s) |
Pierre-Clement A. Simon, Cailon Frank, Long-Qing Chen, Mark Daymond, Michael Tonks, Arthur T Motta |
| On-Site Speaker (Planned) |
Pierre-Clement A. Simon |
| Abstract Scope |
A fraction of the hydrogen produced by waterside corrosion of the zirconium nuclear fuel cladding material in light water reactors is picked up by the cladding, and precipitates into brittle hydrides once the solid solubility limit is reached. Embrittlement of the zirconium due to both circumferential and radial hydrides through the material thickness depends on the exact microstructure and connectivity of the hydride particle network. However, quantifying hydride microstructure is challenging, and several of the metrics currently being used have significant shortcomings. A new metric, the Radial Hydride Continuous Path (RHCP), has been developed using image analysis and implemented using a genetic algorithm to quantify hydride microstructures in relation to their potential effect on crack propagation through the cladding thickness. The RHCP is compared against existing metrics, demonstrating a more precise assessment of the effect of hydrides on cladding integrity. |
| Proceedings Inclusion? |
Planned: |