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 language | English |
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| Title of host publication | Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 |
| Publisher | American Nuclear Society |
| Pages | 1636-1645 |
| Number of pages | 10 |
| ISBN (Electronic) | 9780894482229 |
| DOIs | |
| State | Published - 2025 |
| Event | 2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 - Denver, United States Duration: Apr 27 2025 → Apr 30 2025 |
Publication series
| Name | Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 |
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Conference
| Conference | 2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 |
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| Country/Territory | United States |
| City | Denver |
| Period | 04/27/25 → 04/30/25 |
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