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.