Original Article
2018, United States Nuclear Regulatory Commission, “APR1400 Final Safety Evaluation,” Available online: https://www.nrc.gov/reactors/new-reactors/large-lwr/design-cert/apr1400/ser-final.html.
1982, Ishii, M. and Mishima, K., “Two-fluid model and hydrodynamic constitutive relations,” Nucl. Eng. Des., Vol.82, pp.107-126.
10.1016/0029-5493(84)90207-32001, United States Nuclear Regulatory Commission, “RELAP5/MOD3.3 Code Manuals,” Idaho National Laboratory.
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)00039-02005, The RELAP5-3D Code Development Team, “RELAP5-3D Code Manula Volume I: Code Structure, System Models and Solution Method,” Idaho National Laboratory.
2011, Emonot, P., Souyri, A., Gandrille, J.L. and Barré, F., “CATHARE-3: A new system code for thermal-hydraulics in the context of the NEPTUNE project,” Nucl. Eng. Des., Vol.241, No.11, pp.4476-4481.
10.1016/j.nucengdes.2011.04.0491999, 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)00039-02025, ANSYS, Inc, “Ansys Fluent,” Available online: https://www.ansys.com/products/fluids/ansys-fluent.
2025, SIEMENS Digital Industries Software, Inc, “Simcenter STAR-CCM+ CFD software,” Available online: https://plm.sw.siemens.com/en-US/simcenter/fluids-thermal-simulation/star-ccm/.
2007, Guelfi, A., Bestion, D., Boucker, M., Boudier, P., Fillion, P., Grandotto, M., Hérard, J.-M., Hervieu, E. and Péturaud, P., “NEPTUNE: a new software platform for advanced nuclear thermal hydraulics,” Nucl. Sci. Eng., Vol.156, No.3, pp.281-324.
10.13182/NSE05-982010, 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.02.2014.0232020, 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.
10.1080/00295639.2020.17276981984, Hochreiter, L.E., Rupprecht, S.D., Dederer, J.T., Wong, S., Rosal, E.R., Sinwell, B.R., Kovdalski, F.J. and Quaglia, R., “PWR FLECHT SEASET Systems and reflux condensation data evaluation and analysis report,” NRC/EPRI/Westinghouse Report No. 14, NUREG/CR-3654.
- 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 :102-122
- Received Date : 2025-06-16
- Revised Date : 2025-08-08
- Accepted Date : 2025-08-13
- DOI :https://doi.org/10.6112/kscfe.2025.30.3.102


Journal of Computational Fluids Engineering








