SiC fiber composite material as fuel cladding is proposed to increase the power density and maximum allowable fuel burnup in light water reactors. Empirical models about thermal properties of the SiC material are developed as a function of operating temperature and neutron fluence. A fuel rod modeling code frapcon2-SiC based on frapcon2 is compiled to predict the performance of SiC cladding when operating. Comparison of the behavior between the SiCf/SiC cladding and Zr-4 cladding in different thickness reveals that higher temperature will get due to the poor thermal conductivity of the SiC. As far as the Conclusion shows that Poor thermal performance of SiC cladding makes the design margin becomes smaller.
- Nuclear Engineering Division
Modeling and Thermal Calculation of Fuel Rod With SiCf/SiC Cladding for LWRs
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Xinyuan, S, Shaoyang, Z, & Aimin, Z. "Modeling and Thermal Calculation of Fuel Rod With SiCf/SiC Cladding for LWRs." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application. Shanghai, China. July 2–6, 2017. V003T02A040. ASME. https://doi.org/10.1115/ICONE25-67078
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