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    열수력 기기해석용 CUPID 코드 개발 및 평가 전략

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    https://www.riss.kr/link?id=A82637380

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    다국어 초록 (Multilingual Abstract) kakao i 다국어 번역

    A three-dimensional thermal-hydraulic code, CUPID, has been developed for the analysis of transient two-phase flows at component scale. The CUPID code adopts a two-fluid three-field model for two-phase flows. A semi-implicit two-step numerical method was developed to obtain numerical solutions on unstructured grids. This paper presents an overview of the CUPID code development and assessment strategy. The governing equations, physical models, numerical methods and their improvements, and the systematic verification and validation processes are discussed. The code couplings with a system code, MARS, and, a three-dimensional reactor kinetics code, MASTER, are also presented.
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    A three-dimensional thermal-hydraulic code, CUPID, has been developed for the analysis of transient two-phase flows at component scale. The CUPID code adopts a two-fluid three-field model for two-phase flows. A semi-implicit two-step numerical method ...

    A three-dimensional thermal-hydraulic code, CUPID, has been developed for the analysis of transient two-phase flows at component scale. The CUPID code adopts a two-fluid three-field model for two-phase flows. A semi-implicit two-step numerical method was developed to obtain numerical solutions on unstructured grids. This paper presents an overview of the CUPID code development and assessment strategy. The governing equations, physical models, numerical methods and their improvements, and the systematic verification and validation processes are discussed. The code couplings with a system code, MARS, and, a three-dimensional reactor kinetics code, MASTER, are also presented.

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    참고문헌 (Reference)

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    10 Barth, T.J, "The design and application of upwind schemes on unstructured meshes" AIAA 1989

    1 Tentner, A, "fluid dynamics modeling of two-phase flow in a boiling water reactor fuel assembly" 2005

    2 Ustinenko, V, "Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis" 238 : 660-670, 2008

    3 Lopez de Bertodano, M, "Two fluid model for two-phase turbulent jets" 179 : 65-74, 1998

    4 Michiyoshi, I, "Turbulence in two-phase bubbly flow" 95 : 253-267, 1986

    5 Yadigaroglu, G, "Trends and needs in experimentation and numerical simulation for LWR safety" 221 : 205-223, 2003

    6 Tomiyama, A, "Transverse migration of single bubbles in simple shear flows" 57 : 1849-1858, 2002

    7 Euh, D.J, "Transport of local two-phase parameters in vertical air/water flow for bubbly and slug flow regime" 2010

    8 "Transient Thermal-Hydraulic and Neutronic Codes Requirements" 97 (97): 1996

    9 Ishii, M, "Thermo-Fluid Dynamics of Two-Phase Flow" Springer 2006

    10 Barth, T.J, "The design and application of upwind schemes on unstructured meshes" AIAA 1989

    11 Drew, D, "The analysis of virtual mass effect in two-phase flow" 5 : 233-272, 1979

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    14 DOMINIQUE BESTION, "STATUS AND PERSPECTIVE OF TWO-PHASE FLOWMODELLING IN THE NEPTUNE MULTISCALE THERMALHYDRAULICPLATFORM FOR NUCLEAR REACTOR SIMULATION" 한국원자력학회 37 (37): 511-524, 2005

    15 CD-adapco, "STAR-CD Version 4.0 Methodology Manual, Chapter 13" CD-adapco 2006

    16 Frink, N.T, "Recent progress toward a three-dimensional unstructured Navier-Stokes flow solver" AIAA 1994

    17 The RELAP5-3D Code Development Team, "RELAP5-3D code manual volume I: Code structure, system models and solution methods" Idaho National Engineering and Environmental Laboratory 2001

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    19 Lahey, R.T, "Phase distribution in complex geometry conduits" 141 : 177-201, 1993

    20 Hosoi, H, "Numerical simulation of air-water two-phase flow in 38 mm diameter pipe by advanced two-fluid model including effects of turbulent diffusion on bubbles" 14-17, 2010

    21 Park, I.K, "Numerical effects of the semi-conservative form of momentum equations for multi-dimensional two-phase flows" 239 : 2365-2371, 2009

    22 Frepoli, C, "Notes on the implementation of a fully-implicit numerical scheme for a two-phase three-field flow model" 225 : 191-217, 2003

    23 Guelfi, A, "NEPTUNE: a new software platform for advanced nuclear thermal hydraulics" 156 (156): 281-324, 2007

    24 Niceno, B, "Multi-scale modeling and analysis of convective boiling: Towards the prediction of CHF in rod bundles, in the December issue of Nuclear Engineering and Technology" 2010

    25 Sato, Y, "Momentum and heat transfer in two-phase bubble flow - I" 7 : 167-177, 1981

    26 Boer, R, "MSLB exercise 2: 3-D kinetics results with RELAP5/PANBOX" American Nuclear Society 2000

    27 Yun, B.J, "Investigation of the downcomer boiling phenomena during the reflood phase of a postulated large-break LOCA in the APR1400" 156 : 56-68, 2006

    28 Weiss, J.M, "Implicit solution of preconditioned Navier-Stokes equations using algebraic multigrid" 37 (37): 1999

    29 Cho, H.K, "Implementation of a second-order upwind method in a semi-implicit two-phase flow code on unstructured meshes" 37 : 606-614, 2010

    30 Kataoka, I, "Generation and size distribution of droplet in annular two-phase flow" 105 : 230-238, 1983

    31 Yoneda, K, "Flow structure and bubble characteristics of steam–water two-phase flow in a large-diameter pipe" 217 : 267-281, 2002

    32 Huh, B.K, "Experimental and Analytical Study of Interfacial Are Transport Phenomena in a Vertical Two-phase Flow" Seoul National University 2005

    33 Nagatake, T, "Establishment of experimental data base on dam-breaking problem for validating interface tracking methods" 2008

    34 DOMINIQUE BESTION, "EXTENSION OF CFD CODES APPLICATION TO TWOPHASE FLOW SAFETY PROBLEMS" 한국원자력학회 42 (42): 365-376, 2010

    35 Jeong, J.J, "Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1" 26 (26): 1611-1642, 1999

    36 JAE JUN JEONG, "DEVELOPMENT AND PRELIMINARY ASSESSMENT OF A THREE-DIMENSIONAL THERMAL HYDRAULICS CODE, CUPID" 한국원자력학회 42 (42): 279-296, 2010

    37 Lee, J.R, "Coupled simulation of component thermal hydraulics and neutron kinetics for a nuclear reactor core with CUPID and MASTER" 2010

    38 Cole, R, "Correlation of bubble departure diameters for boiling of saturated liquids" 65 (65): 211-213, 1969

    39 Venkatakrishnan, V, "Convergence to steady state solutions of the Euler equations on unstructured grids with limiters" 118 : 120-130, 1995

    40 Cho, H.K, "Constitutive relations and a second-order interpolation scheme for the semi-implicit two-phase flow solver, CUPID" 2009

    41 Tentner, A, "Computational fluid dynamics modeling of two-phase flow topologies in a boiling water reactor fuel assembly" 2008

    42 Yadigaroglu, G, "Computational fluid dynamics for nuclear applications: From CFD to multi-scale CMFD" 235 (235): 153-164, 2005

    43 Cho, H.K, "Computational analysis of downcomer boiling phenomena using a component thermal hydraulic analysis code CUPID" 2010

    44 Lee, S.Y, "COBRA/RELAP5; A merged version of the COBRA-TF and RELAP5/MOD3 codes" 99 : 177-187, 1992

    45 AEA, "CFX-4 Solver Manual" UK 1997

    46 Joo, H.G, "Analysis of the OECD MSLB benchmark problem using the refined core thermal-hydraulic nodalization feature of the MARS/MASTER code" 142 : 166-179, 2003

    47 Antal, S.P, "Analysis of phase distribution in fully developed laminar bubbly two-phase flow" 7 : 635-652, 1991

    48 Lee, H, "An improved numerical scheme to evaluate the pressure gradient on unstructured meshes for two-phase flow analysis" 37 : 1273-1279, 2010

    49 Ioilev, A, "Advances in the modeling of cladding heat transfer and critical heat flux in boiling water reactor fuel assemblies" 2007

    50 Tentner, A, "Advances in computational fluid dynamics modeling of two-phase flow in a boiling water reactor fuel assembly" 2006

    51 Staetke, H, "Advanced three-dimensional two-phase flow simulation tools for application to reactor safety (ASTAR)" 235 : 379-400, 2005

    52 Jeong, J.J, "A semi-implicit numerical scheme for transient two-phase flows on unstructured grids" ELSEVIER SCIENCE SA 238 (238): 3403-3412, 2008

    53 Liles, D.R, "A semi-implicit method for two-phase fluid dynamics" 26 : 390-407, 1978

    54 Mathur, S.R, "A pressure-based method for unstructured meshes" Part B (Part B): 195-215, 1997

    55 Jeong, J.J, "A coupled analysis of system thermal-hydraulics and three-dimensional reactor kinetics for a 12-finger control element assembly drop event in a PWR plant" 37 : 1580-1587, 2010

    56 Yoon, H.Y, "A continuity based semi-implicit scheme for transient two-phase flows" 47 (47): 779-789, 2010

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    연월일 이력구분 이력상세 등재구분
    2027 평가 재인증평가 신청대상 (재인증)
    2021-01-01 등재 등재학술지 유지 (재인증) KCI등재
    2018-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2015-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2011-01-01 등재 등재 1차 FAIL (등재유지) KCI등재
    2009-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2006-01-01 등재 등재학술지 선정 (등재후보2차) KCI등재
    2005-06-16 학술지명변경 외국어명 : Jpurnal of Computatuonal Fluids Engineering -> Korean Society of Computatuonal Fluids Engineering KCI등재후보
    2005-01-01 등재 등재후보 1차 PASS (등재후보1차) KCI등재후보
    2004-01-01 등재 등재후보 1차 FAIL (등재후보1차) KCI등재후보
    2002-07-01 등재 등재후보학술지 선정 (신규평가) KCI등재후보
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    2016 0.2 0.2 0.19
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