About this Abstract |
Meeting |
2020 TMS Annual Meeting & Exhibition
|
Symposium
|
Computational Materials Science and Engineering of Materials in Nuclear Reactors
|
Presentation Title |
A Physical Model of Zircaloy Corrosion in Water for Simulating Nuclear Reactor Clad Response |
Author(s) |
Jaime Marian, Qianran Yu, Peng Wang, Michael Reyes, Asghar Aryanfar, Gary Was |
On-Site Speaker (Planned) |
Jaime Marian |
Abstract Scope |
The long-term integrity of the fuel elements in the reactor core is highly dependent on the response of Zirconium cladding to corrosion, and it is therefore imperative that reliable models of oxide scale buildup be devised. In this work, we present a model of the evolution of the Zr oxide layer accounting for thermo-migration and electro-migration of oxygen transport in the clad, in addition to standard thermally-activated diffusion. As well, the model is guided by quantum mechanical calculations of the stability of zirconium-oxygen compounds. Irradiation is captured in the form of radiation enhanced diffusion, with model predictions informed by well-controlled proton irradiation experiments. Finally, we also provide results of the formation and growth of hydride platelets below the oxide layer using kinetic rate theory models fitted with atomistic data. |
Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |