1 J.J. JEONG, "THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY" 한국원자력학회 42 (42): 636-655, 2010
2 "SALOME website"
3 윤한영, "Recent Improvements in the CUPID Code for a Multi-Dimensional Two-Phase Flow Analysis of Nuclear Reactor Components" 한국원자력학회 46 (46): 655-666, 2014
4 OECD, "Proceedings of the OECD/NEA/CSNI specialist meeting on boron dilution reactivity transient"
5 S. Kliem, "OECD PKL3 project" 2016
6 S. Kliem, "OECD PKL2 project" 2012
7 Boumaza, M., "Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles" 280 : 362-371, 2014
8 Han Young Yoon, "Multi-Scale Thermal-Hydraulic Analysis of PWRs using the CUPID Code" 한국원자력학회 44 (44): 831-846, 2012
9 Boyd, C., "Modeling approach and predictions of boron mixing in core bypass of ESBWR" 2008
10 Cronenberg, A.W., "Memorandum to Kress, Bonaca, Uhrig, Wallis, Powers, Apostolakis: Summary of boron dilution issues and regulatory actions" U. S. Nuclear Regulatory Commission 2000
1 J.J. JEONG, "THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY" 한국원자력학회 42 (42): 636-655, 2010
2 "SALOME website"
3 윤한영, "Recent Improvements in the CUPID Code for a Multi-Dimensional Two-Phase Flow Analysis of Nuclear Reactor Components" 한국원자력학회 46 (46): 655-666, 2014
4 OECD, "Proceedings of the OECD/NEA/CSNI specialist meeting on boron dilution reactivity transient"
5 S. Kliem, "OECD PKL3 project" 2016
6 S. Kliem, "OECD PKL2 project" 2012
7 Boumaza, M., "Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles" 280 : 362-371, 2014
8 Han Young Yoon, "Multi-Scale Thermal-Hydraulic Analysis of PWRs using the CUPID Code" 한국원자력학회 44 (44): 831-846, 2012
9 Boyd, C., "Modeling approach and predictions of boron mixing in core bypass of ESBWR" 2008
10 Cronenberg, A.W., "Memorandum to Kress, Bonaca, Uhrig, Wallis, Powers, Apostolakis: Summary of boron dilution issues and regulatory actions" U. S. Nuclear Regulatory Commission 2000
11 Jayaraju, S.T., "Large eddy simulation for an inherent boron dilution transient" 262 : 484-498, 2013
12 Rohde, U., "Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor" 237 : 1639-1655, 2007
13 Hagen, E.W., "Evaluation of events involving unplanned boron dilutions in nuclear power plants" U. S. Nuclear Regulatory Commission 1982
14 FZR, "European project FLOMIX-R:Forschungszentrum Rossendorf, The European project FLOMIX-R: description of the slug mixing and buoyancy related experiment at the different test facilities" FZR 2005
15 정재준, "DEVELOPMENT AND PRELIMINARY ASSESSMENT OF A THREE-DIMENSIONAL THERMAL HYDRAULICS CODE, CUPID" 한국원자력학회 42 (42): 279-296, 2010
16 Do, S.J., "CUPID2.2 Code Mathematical Models and Solution Methods" Korea Atomic Energy Research Institute 2018
17 Dury, T.V., "CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies" 238 : 577-589, 2008
18 Nuclear Energy Agency, "Best Practice Guideline for the Use of CFD in Nuclear Reactor Safety Application-Revision" OECD NEA 2015