Submitted:
05 February 2026
Posted:
09 February 2026
You are already at the latest version
Abstract
Keywords:
1. Introduction
2. Implementation of Molten-Salt Thermophysical Properties
2.1. Density Correlation
2.2. Heat Capacity Correlation
2.3. Thermal Conductivity Correlation
2.4. Viscosity Correlation
2.5. Summary of Property Behavior
3. Verification Against the de Vahl Davis Benchmark
3.1. Problem Description
3.2. Nusselt Number Evaluation Method
3.3. Mesh Sensitivity Assessment
3.4. Comparison with Benchmark Solution




3.5. Temperature-Variation Sensitivity


4. Assessment of the Boussinesq Approximation
4.1. Full Variable-Density and Boussinesq Models
4.2. Numerical Methodology
- the full variable-density formulation, and
- the Boussinesq formulation, in which density is treated as constant in all momentum terms except for buoyancy.
4.3. Linearization of Density
4.4. Results and Discussion
5. Conclusions
Author Contributions
Funding
Acknowledgments
Conflicts of Interest
Abbreviations
| Latin symbols | |
| Specific heat capacity | |
| g | Gravitational acceleration |
| Cavity height and width | |
| Molar mass of component i | |
| Local Nusselt number | |
| Average Nusselt number at the hot wall | |
| Prandtl number | |
| Rayleigh number | |
| R | Universal gas constant |
| T | Temperature |
| Dimensionless temperature | |
| Mole fraction of component i | |
| Greek symbols | |
| Density | |
| Dynamic viscosity | |
| Thermal conductivity | |
| Thermal expansion coefficient | |
| Relative error of Nusselt number | |
| Subscripts and indices | |
| i | Index of component (i-th element) |
| Hot wall temperature | |
| Cold wall temperature | |
| Temperature difference () | |
| Melting temperature of component i |
References
- Bettis, E.S.; et al. The aircraft reactor experiment—design and construction. Nucl. Sci. Eng. 1957, 2, 804–825. [Google Scholar] [CrossRef]
- MacPherson, H.G. The molten salt reactor adventure. Nucl. Sci. Eng. 1985, 90, 374–380. [Google Scholar] [CrossRef]
- Terrestrial Energy Inc. Integral Molten Salt Reactor (IMSR) Technology Overview. Available online: https://www.terrestrialenergy.com (accessed on 29 January 2026).
- Power, Kairos. License to Build: Progress on Hermes and the ETU Series. Available online: https://kairospower.com (accessed on 29 January 2026).
- Energy, Saltfoss. Compact Molten Salt Reactor (CMSR)—Technology Overview. Available online: https://saltfoss.com (accessed on 29 January 2026).
- Lee, C.; Yeo, D.; Koo, G.H. A preliminary thermal analysis and modeling study of MSRE freeze valve for K-MSR valve development. In Proceedings of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2024. [Google Scholar]
- Jeong, J.; Koo, G.H.; Kim, T. Preliminary thermal analysis of the K-MSR. Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2024. [Google Scholar]
- Korea Atomic Energy Research Institute. KAERI and Seaborg APS Sign an MOU on MSR Development. Available online: https://www.kaeri.re.kr (accessed on 29 January 2026).
- U.S. Nuclear Regulatory Commission. RELAP5/MOD3.3 Code Manuals. Idaho National Laboratory, 2001. [Google Scholar]
- Robert, M.; Farvacque, M.; Parent, M.; Faydide, B. CATHARE 2 V2.5: A fully validated CATHARE version for various applications. In Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, 5–9 October 2003. [Google Scholar]
- Jeong, J.J.; Ha, K.S.; Chung, B.D.; Lee, W.J. Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1. Ann. Nucl. Energy 1999, 26, 1611–1642. [Google Scholar] [CrossRef]
- Lim, H.S. KAERI/TR-8662/2021; GAMMA+ 2.0 Volume II: Theory Manual. Korea Atomic Energy Research Institute, 2021.
- Tak, N.I.; Kim, M.S.; Lee, C.; Koo, G.H. Improvement of GAMMA+ code for system transient and thermo-fluid safety analysis of sodium-cooled fast reactors. Nucl. Eng. Des. 2022, 399, 112002. [Google Scholar] [CrossRef]
- Yeo, D.; Lee, C.; Koo, G.H. Parametric study of the fuel salt drain system design of K-MSR. Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2024. [Google Scholar]
- Jeong, J.J.; Yoon, H.Y.; Park, I.K.; Cho, H.K. The CUPID code development and assessment strategy. Nucl. Eng. Technol. 2010, 42, 636–655. [Google Scholar] [CrossRef]
- Yoon, H.Y.; Lee, J.R.; Kim, H.; Park, I.K.; Song, C.H.; Cho, H.K.; Jeong, J.J. Recent improvements in the CUPID code for a multi-dimensional two-phase flow analysis of nuclear reactor components. Nucl. Eng. Technol. 2014, 46, 655–672. [Google Scholar] [CrossRef]
- Yoon, H.Y.; Park, I.K.; Lee, J.R.; Lee, S.J.; Cho, Y.J.; Do, S.J.; Cho, H.K.; Jeong, J.J. A multiscale and multiphysics PWR safety analysis at a subchannel scale. Nucl. Sci. Eng. 2020, 194, 633–649. [Google Scholar] [CrossRef]
- de Vahl Davis, G. Natural convection of air in a square cavity: A benchmark numerical solution. Int. J. Numer. Methods Fluids 1983, 3, 249–264. [Google Scholar] [CrossRef]







| Rayleigh Number () | ||||
|---|---|---|---|---|
| Mesh resolution | ||||
| KCl– | 8.760 | 1.2582 | 2.7108 | 4.3800 |
| NaCl–– | 1.0377 | 1.4905 | 3.2112 | 5.1890 |
| Calculation | ||||
|---|---|---|---|---|
| de Vahl Davis | 1.118 | 2.243 | 4.519 | 8.800 |
| CUPID-MSR (KCl–) | 1.1253 (0.66)* | 2.1815 (2.74)* | 4.6180 (2.19)* | 9.1401 (3.86)* |
| CUPID-MSR (NaCl––) | 1.1137 (0.38)* | 2.2315 (0.51)* | 4.5599 (0.91)* | 8.9568 (1.78)* |
Disclaimer/Publisher’s Note: The statements, opinions and data contained in all publications are solely those of the individual author(s) and contributor(s) and not of MDPI and/or the editor(s). MDPI and/or the editor(s) disclaim responsibility for any injury to people or property resulting from any ideas, methods, instructions or products referred to in the content. |
© 2026 by the authors. Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (http://creativecommons.org/licenses/by/4.0/).