Abstract
The Monte Carlo code Serpent 2 was used to generate homogenized few-group constants for the nodal diffusion analysis of the Molten Salt Reactor Experiment (MSRE) zero-power criticality benchmark. A 3D full core model of MSRE was built with Serpent 2 and SCALE/Shift. A good agreement was achieved for the multiplication factor between Serpent 2, SCALE/Shift and the benchmark reference result, demonstrating the consistency between the models. The nodal diffusion analysis of a 3D graphite core model of MSRE was performed with the few-group constants generated by Serpent 2 using nodal diffusion code PARCS. A good agreement between Serpent 2 and PARCS was observed demonstrating the feasibility of using Serpent 2 as a few-group constant generator and using PARCS as a nodal diffusion core simulator for the deterministic MSRE analysis.
| 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 2021 |
| Publisher | American Nuclear Society |
| Pages | 530-539 |
| Number of pages | 10 |
| ISBN (Electronic) | 9781713886310 |
| DOIs | |
| State | Published - 2021 |
| Event | 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 - Virtual, Online Duration: Oct 3 2021 → Oct 7 2021 |
Publication series
| Name | Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 |
|---|
Conference
| Conference | 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 |
|---|---|
| City | Virtual, Online |
| Period | 10/3/21 → 10/7/21 |
Funding
The authors would like to thank Rike Bostelmann from Oak Ridge National Laboratory for helpful discussions.
Keywords
- MC few-group constant
- MSRE
- PARCS
- Serpent 2
- nodal diffusion