Abstract
This paper describes several recent enhancements added to the Shift Monte Carlo (MC) code package, which is part of the ORNL-developed SCALE code system, targeting multigroup cross section generation. The two main new enhancements include the ability to produce a multigroup microscopic cross-section library and the ability to produce multigroup macroscopic cross on an overlay geometry. The use of these capabilities is demonstrated herein by applying Shift to sections two benchmark problems: one for a sodium-cooled fast reactor and one for a high-temperature gas-cooled pebble-bed reactor. Comparisons of cross sections, eigenvalues, and reaction rates with other code packages show consistency and agreement. Two-step neutronics calculations were performed with Griffin using the MC-generated cross sections, and comparisons of eigenvalues and reaction rates showed good agreement with reference solutions to within the current known dlimitations.
| Original language | English |
|---|---|
| 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 | 973-983 |
| Number of pages | 11 |
| 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 |
|---|
Conference
| Conference | 2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 |
|---|---|
| Country/Territory | United States |
| City | Denver |
| Period | 04/27/25 → 04/30/25 |
Funding
This work was supported by the US Department of Energy (DOE) Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. The authors would like to thank INL and Argonne for providing base models and collaborating on running and interpreting Griffin and MC-3 results. This research made use of Idaho National Laboratory’s High Performance Computing systems located at the Collaborative Computing Center and supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Keywords
- Cross section generation
- Monte Carlo
- Shift