|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Implementation and Validation of a Physically-based Fuel Cladding Oxidation Model in BISON Nuclear Fuel Performance Code
||Léo Borrel, Adrien Couet
|On-Site Speaker (Planned)
Correctly predicting the fuel cladding mechanical behavior during LOCA is critical for nuclear safety analysis as the fuel rod needs to maintain its coolable geometry throughout the LOCA transient. The physically-based Coupled Current Charge Compensation (C4) model is developed to predict critical oxidation-related data (i) oxide and oxygen-stabilized α-Zr layer growth kinetics, (ii) hydrogen pickup kinetics (iii) oxygen concentration profile in the cladding, for multiple zirconium alloy for both operating and accidental conditions (LOCA), with a <I>unique</I> set of parameters. These predictions are particularly critical since the mechanical integrity of the cladding upon a LOCA transient is ultimately dependent on the oxygen content in the prior-β phase. Implementation of this model in the nuclear fuel performance code BISON requires the use of Extended Finite Element Method to mesh the growing oxide. Electron Probe Micro Analysis has been used on high-temperature oxidized zirconium samples to obtain data for model validation.
||Planned: Supplemental Proceedings volume