Enrichment Interpolation for High-Assay Low-Enriched Uranium Fuel Macroscopic Cross Section for Polaris/PARCS

Junsu Kang, Andrew M. Ward, Ugur Mertyurek, Thomas J. Downar

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

A method was developed to estimate a set of multigroup cross sections for core design by interpolating between a set of existing macroscopic cross sections at different fuel e nrichments. A Gaussian process (GP) interpolation method was used with adaptive sampling in order to minimize the number of required lattice physics calculations. The interpolation was applied to pressurized water reactor (PWR) fuel assemblies containing High-Assay Low-Enriched Uranium (HALEU) fuel pins. The accuracy of the interpolated cross section libraries was assessed by a direct comparison with a cross section set generated by a lattice physics calculation at the interpolated enrichment. A specified accuracy was achievable by using the adaptive sampling method.

Original languageEnglish
Title of host publicationProceedings of the International Conference on Physics of Reactors, PHYSOR 2024
PublisherAmerican Nuclear Society
Pages2184-2193
Number of pages10
ISBN (Electronic)9780894487972
DOIs
StatePublished - 2024
Event2024 International Conference on Physics of Reactors, PHYSOR 2024 - San Francisco, United States
Duration: Apr 21 2024Apr 24 2024

Publication series

NameProceedings of the International Conference on Physics of Reactors, PHYSOR 2024

Conference

Conference2024 International Conference on Physics of Reactors, PHYSOR 2024
Country/TerritoryUnited States
CitySan Francisco
Period04/21/2404/24/24

Keywords

  • Cross Section
  • Gaussian Process
  • HALEU
  • PARCS

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