Nuclear Data Impact on HTR-10 Pebble Bed Reactor Metrics

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Abstract

This study investigates the impact of nuclear data on selected key core metrics for the HTR-10 pebble-bed reactor, as part of a broader project that aims to facilitate the identification of nuclear data deficiencies and needs in the US Nuclear Data Program databases that impact the safety of advanced reactors. This study’s focus extends from analyzing a fresh fuel core configuration to examining an equilibrium core, in which additional nuclides significantly influence the reactor’s behavior to the fresh fuel configuration. Sensitivities to and uncertainties due to nuclear data were determined compared for the effective multiplication factor (keff) and the temperature of fuel and temperature of pebble graphite reactivity responses of two full-core models of the HTR-10: an initial core with fresh fuel and an equilibrium core. The underlying simulations were performed using the SCALE code system with the ENDF/B-VII.1 nuclear data library. With respect to sensitivities, the results indicate that v-, fission, and (n, γ) reactions of 235U, elastic scattering and (n, γ) of graphite, and (n, α) of 10B are significant nuclides and reactions for both fresh fuel and equilibrium cores. For the equilibrium core, additional nuclides and reactions come into play, including v-, fission, (n, γ) of 239Pu and 241Pu, as well as (n, γ) reactions of fission products such as 143Nd, 149Sm, and 135Xe. With respect to uncertainties, v- of 235U and elastic scattering and (n, γ) in graphite are among the top contributors to the nuclear data-induced uncertainty of quantities considered for both core configurations. Specific nuclide-reaction pairs for the equilibrium core are (n, γ) of 135Xe, elastic scattering of 144Nd, and fission and (n, γ) of 239Pu.

Original languageEnglish
Title of host publicationProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
PublisherAmerican Nuclear Society
Pages1636-1645
Number of pages10
ISBN (Electronic)9780894482229
DOIs
StatePublished - 2025
Event2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 - Denver, United States
Duration: Apr 27 2025Apr 30 2025

Publication series

NameProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025

Conference

Conference2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
Country/TerritoryUnited States
CityDenver
Period04/27/2504/30/25

Funding

This work was performed under the support of the Department of Energy (DOE) Office of Science Nuclear Data Program.

Keywords

  • advanced reactors
  • nuclear data
  • pebble bed reactor
  • sensitivity coefficients
  • uncertainty analysis

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