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• W2890981773 abstract "Abstract A detailed analysis of neutronics, core thermal-hydraulics, and fuel performance has been developed to predict the thermo-mechanical failures of all the metallic fuel rods in a sodium-cooled fast reactor. The neutronics analysis provides a reload pattern for fuel assemblies and power/flux spatial distributions for each fuel rod. The core thermal-hydraulics allows the calculation of the cladding temperatures via subchannel analysis. The fuel performance analysis evaluates the thermo-mechanical integrity of all the fuel rods by considering the detailed spatial and temporal variations of the thermal power, neutron flux, and cladding temperature during the in-core lifetime of each fuel assembly. This analysis leads to improved computational accuracy and provides more comprehensive physical information for each code than a conventional one-dimensional fuel performance calculation. It is evident that, compared with a simple conservative one-dimensional analysis, the present method will improve plant performance while maintaining the thermal margin. The developed analysis has been applied to evaluate the fuel performance of a Prototype Gen IV sodium-cooled fast reactor candidate core by considering the uncertainties of the design parameters." @default.
• W2890981773 created "2018-09-27" @default.
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• W2890981773 date "2018-12-01" @default.
• W2890981773 modified "2023-09-26" @default.
• W2890981773 title "Thermo-mechanical behavior of all the metallic fuel rods in a sodium-cooled fast reactor" @default.
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• W2890981773 doi "https://doi.org/10.1016/j.nucengdes.2018.09.006" @default.
• W2890981773 hasPublicationYear "2018" @default.
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