Original Article
1957, Bettis, E.S., Schroeder, R.W., Cristy, G.A., Savage, H.W., Affel, R.G. and Hemphill, L.F., “The aircraft reactor experiment - design and construction,” Nucl. Sci. Eng., Vol.2, No.6, pp.804-825.
10.13182/NSE57-A354951985, MacPherson, H.G., “The molten salt reactor adventure,” Nucl. Sci. Eng., Vol.90, No.4, pp.374-380.
10.13182/NSE90-3742024, Terrestrial Energy Inc., “Integral Molten Salt Reactor (IMSR) Technology Overview,” Terrestrial Energy. Available online: https://www.terrestrialenergy.com.
2024, Kairos Power, “License to Build: Progress on Hermes and the ETU Series,” Available online: https://kairospower.com.
2025, Saltfoss Energy, “Compact Molten Salt Reactor (CMSR) – Technology Overview,” Saltfoss Energy, Available online: https://saltfoss.com.
2024, Lee, C., Yeo, D. and Koo, G.H., “A preliminary thermal analysis and modeling study of MSRE freeze valve for K-MSR valve development,” Proc. Korean Nucl. Soc. Spring Meeting, Jeju, Korea, May.
2024, Jeong, J., Koo, G.H. and Kim, T., “Preliminary thermal analysis of the K-MSR,” Trans. Korean Nucl. Soc. Spring Meeting, Jeju, Korea, May 9-10, Korea Atomic Energy Research Institute.
2024, Korea Atomic Energy Research Institute, “KAERI and Seaborg APS sign an MOU on MSR development,” Available online: https://www.kaeri.re.kr.
2003, Robert, M., Farvacque, M., Parent, M. and Faydide, B., “CATHARE 2 V2.5: A Fully Validated CATHARE Version for Various Applications,” Proc. 10th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH 10), Seoul, Korea, Oct. 5-9.
1999, Jeong, J.J., Ha, K.S., Chung, B.D. and Lee, W.J., “Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1,” Ann. Nucl. Energy, Vol.26, No.18, pp.1611-1642.
10.1016/S0306-4549(99)00039-02021, Lim, H.S., “GAMMA+ 2.0 Volume II: Theory Manual,” KAERI/TR-8662/2021, Korea Atomic Energy Research Institute.
2022, Tak, N.I., Kim, M.S., Lee, C. and Koo, G.H., “Improvement of GAMMA+ code for system transient and thermo-fluid safety analysis of sodium-cooled fast reactors,” Nucl. Eng. Des., Vol.399, 112002.
10.1016/j.nucengdes.2022.1120022024, Yeo, D., Lee, C. and Koo, G.H., “Parametric study of the fuel salt drain system design of K-MSR,” Trans. Korean Nucl. Soc. Spring Mtg., Jeju, Korea, May 9-10, Korea Atomic Energy Research Institute.
2010, Jeong, J.J., Yoon, H.Y., Park, I.K. and Cho, H.K.. “The CUPID code development and assessment strategy,” Nucl. Eng. Technol., Vol.42, No.6, pp.636-655.
10.5516/NET.2010.42.6.6362014, Yoon, H.Y., Lee, J.R., Kim, H., Park, I.K., Song, C.-H., Cho, H.K. and Jeong, J.J., “Recent improvements in the CUPID code for a multi-dimensional two-phase flow analysis of nuclear reactor components,” Nucl. Eng. Technol., Vol.46, No.5, p.655.
10.5516/NET.02.2014.023- Publisher :Korean Society for Computational Fluids Engineering
- Publisher(Ko) :한국전산유체공학회
- Journal Title :Journal of Computational Fluids Engineering
- Journal Title(Ko) :한국전산유체공학회지
- Volume : 30
- No :3
- Pages :123-135
- Received Date : 2025-06-16
- Revised Date : 2025-07-08
- Accepted Date : 2025-07-14
- DOI :https://doi.org/10.6112/kscfe.2025.30.3.123


Journal of Computational Fluids Engineering








