A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON
- 1. University of Florida, Gainesville, FL (United States)
- 2. Los Alamos National Laboratory, Los Alamos, NM (United States)
Description
Highlights: • A new constituent redistribution model was added to the BISON fuel performance code. • The model is applicable to uranium-zirconium and uranium-plutonium-zirconium fuels. • It leverages pycalphad thermodynamic calculations to improve performance. • Its binary predictions are acceptable but ternary predictions require improvement. • The model has been coupled to BISON thermomechanics at the engineering scale. A CALPHAD-informed (Computer Coupling of Phase Diagrams and Thermochemistry) constituent redistribution model was developed for Zr-based metallic fuels and incorporated into the BISON fuel performance code. Three uncertain model parameters associated with and phase kinetics were calibrated using integral test data from U-Zr fuel elements irradiated in Experimental Breeder Reactor II. The calibrated constituent redistribution model was shown to predict the behavior of U-Zr fuels with excellent accuracy. Model predictions for U-Pu-Zr fuels were physically reasonable but less accurate. Reduction of uncertainties in the ternary phase transition temperatures and collection of kinetic data for the phase are expected to improve the model's ternary predictions. Finally, the new model was coupled to existing thermomechanics models in BISON to simulate irradiation of an entire U-Zr fuel element, demonstrating its ability to accurately predict the behavior of U-Zr fuels with realistic geometries and mesh resolutions at the engineering scale.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2020.152657Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2020.152657;
- PII
- S0022311520312654;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 544
- Journal Page Range
- vp.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54086323
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BREEDER REACTORS; COMPUTERIZED SIMULATION; FUEL ELEMENTS; GEOMETRY; IRRADIATION; KINETICS; NUCLEAR FUELS; PERFORMANCE; PHASE DIAGRAMS; PHASE TRANSFORMATIONS; PLUTONIUM; THERMODYNAMICS; TRANSITION TEMPERATURE; URANIUM; ZIRCONIUM
- Descriptors DEC
- ACTINIDES; DIAGRAMS; ELEMENTS; ENERGY SOURCES; FUELS; INFORMATION; MATERIALS; MATHEMATICS; METALS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Copyright
- Copyright (c) 2020 Elsevier B.V. All rights reserved.