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 language | English |
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| Title of host publication | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024 |
| Publisher | American Nuclear Society |
| Pages | 2184-2193 |
| Number of pages | 10 |
| ISBN (Electronic) | 9780894487972 |
| DOIs | |
| State | Published - 2024 |
| Event | 2024 International Conference on Physics of Reactors, PHYSOR 2024 - San Francisco, United States Duration: Apr 21 2024 → Apr 24 2024 |
Publication series
| Name | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024 |
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Conference
| Conference | 2024 International Conference on Physics of Reactors, PHYSOR 2024 |
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| Country/Territory | United States |
| City | San Francisco |
| Period | 04/21/24 → 04/24/24 |
Funding
The authors would like to acknowledge the support by Department of Energy, and Oak Ridge National Laboratory, UT-Battelle, LLC under award number CW44749.
Keywords
- Cross Section
- Gaussian Process
- HALEU
- PARCS