Validation of bison calculation of hydrogen distribution by comparison to experiment

Evrard Lacroix, Arthur Motta

Research output: Chapter in Book/Report/Conference proceedingConference contribution

4 Scopus citations


During normal operation in nuclear reactors, the nuclear fuel cladding corrodes as a result of exposure to high temperature cooling water. During 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 measured in a nuclear fuel rod. which had undergone a five cycles exposure. The prediction of hydrogen distribution show good agreement with the post irradiation measurement, indicating the promise of this benchmarking method.

Original languageEnglish (US)
Title of host publicationTMS Annual Meeting
PublisherMinerals, Metals and Materials Society
Number of pages10
ISBN (Electronic)9781119225836
StatePublished - 2016
Event145th Annual Meeting and Exhibition, TMS 2016 - Nashville, United States
Duration: Feb 14 2016Feb 18 2016

Publication series

NameTMS Annual Meeting


Other145th Annual Meeting and Exhibition, TMS 2016
Country/TerritoryUnited States

All Science Journal Classification (ASJC) codes

  • Condensed Matter Physics
  • Mechanics of Materials
  • Metals and Alloys


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