Abstract
The Molten Salt Reactor (MSR) is a Generation IV advanced fission reactor design in which the coolant, and in some cases the fuel itself, is in the form of liquid molten alkali-halide salts with a fluoride or chloride ionic base. In liquid-fueled MSRs, reactor refueling may be performed online, where fresh fuel salt is added to the core during operation without the need for shutdown periods. Refueling for these reactor designs is typically modeled using either a batch or continuous refueling approach, both of which can be simulated with the SCALE 6.3.1 and Serpent-2 code systems. However, the specific manner in which they are implemented can vary depending upon the rate of refueling, whether the refueling rate is constant or variable, and consideration of salt drainage desired for systems where the in-core salt volume is kept constant. In a novel MSR fuel cycle concept termed the “Sourdough” fuel cycle, fuel salt is allowed to “grow” within the core, with excess salt either being transferred to an external holding tank to maintain a constant core volume or diverted to an upper plenum within the core to allow for volume growth. In this work, continuous refueling was modeled in a thermal-spectrum, LEU-fueled, small MSR design operating with the Sourdough fuel cycle using the SCALE 6.3.1 and Serpent-2 codes. Two different continuous refueling approaches were simulated, with the performance of each being compared to determine which is most suitable for use with the Sourdough fuel cycle concept.
| 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 | 122-131 |
| 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 |
|---|
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 research was made possible through a University Nuclear Leadership Program (UNLP) Fellowship award provided by the U.S. Department of Energy Office of Nuclear Energy, award number DE-NE0009082, for which the authors are genuinely grateful.
Keywords
- Molten salt reactor
- SCALE
- Serpent
- fuel cycle
- online refueling
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