Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment

Greenquist, Ian; Cunningham, Kaylee M.; Hu, Jianwei; Powers, Jeffrey J.; Crawford, Douglas C.

doi:10.1016/j.jnucmat.2021.152997

Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment

Journal Article · Thu Apr 29 00:00:00 EDT 2021 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2021.152997· OSTI ID:1798613

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Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Florida, Gainesville, FL (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

Metallic nuclear fuels are subject to research and development for use in advanced reactors. Robust, accurate metallic fuel performance models are important for the design, safety analysis, and licensing of these reactors. However, metallic fuel performance models require additional development; they are not as mature as UO₂ fuel performance models. A benchmark case based on the IFR-1 experiment was developed to better gauge the accuracy of existing models, identify models for high-priority development, and potentially quantify any future improvements made by further model development.This work collected publicly available information on the IFR-1 experiment and used it to develop the benchmark case. Fuel behavior during the IFR-1 irradiation was simulated by using the fuel performance code BISON, and the predicted results were compared with postirradiation examination data from the IFR-1 experiment. Furthermore, a sensitivity study and tuning studies were performed as a preliminary investigation into the causes of inaccurate temperature and dimensional change predictions.The benchmark predicted reasonably accurate values for the burnup and fission gas release. There was error in the predicted temperatures, which could be explained by uncertainty in the input parameters and legacy temperatures. BISON over-predicted dimensional changes in the fuel and cladding. The sensitivity study showed that the dimensional changes were most sensitive to the fuel swelling anisotropy and the cladding void swelling model. Future benchmark and model development should focus on cladding swelling behaviors to improve dimensional change predictions.

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1798613

Alternate ID(s):: OSTI ID: 1815060

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 0 Vol. 553; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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