|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Computational Materials Engineering for Nuclear Reactor Applications
||Validation of BISON Calculation of Hydrogen Distribution by Comparison to Experiment
||Evrard Lacroix, Arthur Motta
|On-Site Speaker (Planned)
During normal operation in nuclear reactors, The nuclear fuel cladding corrodes as a result of exposure to high temperature cooling water. As a result of this process, hydrogen can enter the zirconium-alloy of the fuel cladding, and under proper conditions, precipitate as brittle hydride platelets which can severely impact cladding ductility and fracture toughness. Hydrogen tends to migrate to and precipitate at colder spots. Because high local hydride concentrations increase the risk of cladding failure, it is important to predict the local hydrogen distribution. To that end, a hydrogen transport model has been implemented in the 3D fuel performance code BISON. In this study, we present an initial attempt of using this model for benchmarking the BISON code as applied to a case of the hydrogen distribution in a nuclear fuel rod, which underwent five cycles exposure. The results show reasonable agreement with experiment, indicating the promise of this benchmarking method.
||Planned: A print-only volume