All Issue

2025 Vol.30, Issue 3 Preview Page

Original Article

30 September 2025. pp. 123-135
Abstract
References
1

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-A35495
2

1985, MacPherson, H.G., “The molten salt reactor adventure,” Nucl. Sci. Eng., Vol.90, No.4, pp.374-380.

10.13182/NSE90-374
3

2024, Terrestrial Energy Inc., “Integral Molten Salt Reactor (IMSR) Technology Overview,” Terrestrial Energy. Available online: https://www.terrestrialenergy.com.

4

2024, Kairos Power, “License to Build: Progress on Hermes and the ETU Series,” Available online: https://kairospower.com.

5

2025, Saltfoss Energy, “Compact Molten Salt Reactor (CMSR) – Technology Overview,” Saltfoss Energy, Available online: https://saltfoss.com.

6

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.

7

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.

8

2024, Korea Atomic Energy Research Institute, “KAERI and Seaborg APS sign an MOU on MSR development,” Available online: https://www.kaeri.re.kr.

9

2001, NRC, US., “RELAP5/MOD3.3 Code Manuals,” Idaho National Laboratory.

10

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.

11

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)00039-0
12

2021, Lim, H.S., “GAMMA+ 2.0 Volume II: Theory Manual,” KAERI/TR-8662/2021, Korea Atomic Energy Research Institute.

13

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.2022.112002
14

2024, 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.

15

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.2010.42.6.636
16

2014, 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
17

2020, Yoon, H.Y., Park, I.K., Lee, J.R., Lee, S.J., Cho, Y.J., Do, S.J., Cho, H.K. and Jeong, J.J., “A multiscale and multiphysics PWR safety analysis at a subchannel scale,” Nucl. Sci. Eng., Vol.194, pp.633-649.

10.1080/00295639.2020.1727698
18

1983, de Vahl Davis, G., “Natural convection of air in a square cavity: a bench mark numerical solution,” Int. J. Numer. Meth. Fluids, Vol.3, No.3, pp.249-264.

10.1002/fld.1650030305
Information
  • 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