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Thermo-mechanical behavior of all the metallic fuel rods in a sodium-cooled fast reactor.
- Source :
-
Nuclear Engineering & Design . Dec2018, Vol. 339, p126-136. 11p. - Publication Year :
- 2018
-
Abstract
- Highlights • A detailed analysis of neutronics, core thermal-hydraulics, and fuel performance has been developed. • Thermo-mechanical failures of all the metallic fuel rods in a SFR are predicted. • This pin-level analysis leads to improved computational accuracy and provides more comprehensive physical information. 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. [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 00295493
- Volume :
- 339
- Database :
- Academic Search Index
- Journal :
- Nuclear Engineering & Design
- Publication Type :
- Academic Journal
- Accession number :
- 132149106
- Full Text :
- https://doi.org/10.1016/j.nucengdes.2018.09.006