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CUPID 코드를 활용한 2×2 봉다발 부수로 유동 해석
이재룡,박익규,김정우,Lee, J.R.,Park, I.K.,Kim, J. 한국전산유체공학회 2016 한국전산유체공학회지 Vol.21 No.4
The CUPID code is a transient, three-dimensional, two-fluid, thermal-hydraulic code designed for a component-scale analysis of nuclear reactor components. The primary objective of this study is to assess the applicability of CUPID to single-phase turbulent flow analyses of $2{\times}2$ rod bundle subchannel. The bulk velocity at the inlet varies from 1.0 m/s up to 2.0 m/s which is equivalent to the fully turbulent flow with the range of Re=12,500 to 25,000. Adiabatic single-phase flow is assumed. The velocity profile at the exit region is quantitatively compared with both experimental measurement and commercial CFD tool. Three different boundary conditions are simulated and quantitatively compared each other. The calculation results of CUPID code shows a good agreement with the experimental data. It is concluded that the CUPID code has capability to reproduce the turbulent flow behavior for the $2{\times}2$ rod bundle geometry.
가압경수로 2상유동 해석 코드 CUPID 병렬화 및 병렬 특성 평가
이재룡(J. R. Lee),윤한영(H. Y. Yoon),최형권(H. G. Choi) 한국전산유체공학회 2014 한국전산유체공학회 학술대회논문집 Vol.2014 No.5
Two-phase thermal hydraulics code, CUPID for multi-dimensional, multi-physics and multi-scale analysis in PWR was parallelized to fulfil the demand for long transient or high-resolved thermal hydraulics calculation. the CUPID code was parallelized based on the domain decomposition method with MPI (Message Passing Interface). For domain decomposition, the CUPID code provides both manual and automatic method with METIS library. For the effective memory management, the CSR (Compressed Sparse Row) format is adopted, which is one of the methods to represent the sparse asymmetric matrix. By performing the verification for the fundamental problem set, the parallelization of the CUPID has been successfully confirmed. In this paper, the characteristics of the parallelized CUPID code were investigated. Since the scalability of a parallel simulation is generally known to be better for fine mesh system, three types of mesh system are considered: 40,000 meshes for coarse system, 320,000 meshes for fine system. In the given geometry, both single- and two-phase calculations are conducted. In addition, two types of preconditioning for matrix solver were compared: diagonal and incomplete LU preconditioning.
CUPID 코드를 활용한 2X2 봉다발 부수로 유동 해석
이재룡(J.R. Lee),박익규(I.K. Park),김정우(J. Kim) 한국전산유체공학회 2016 한국전산유체공학회지 Vol.21 No.4
The CUPID code is a transient, three-dimensional, two-fluid, thermal-hydraulic code designed for a component-scale analysis of nuclear reactor components. The primary objective of this study is to assess the applicability of CUPID to single-phase turbulent flow analyses of 2×2 rod bundle subchannel. The bulk velocity at the inlet varies from 1.0 m/s up to 2.0 m/s which is equivalent to the fully turbulent flow with the range of Re=12,500 to 25,000. Adiabatic single-phase flow is assumed. The velocity profile at the exit region is quantitatively compared with both experimental measurement and commercial CFD tool. Three different boundary conditions are simulated and quantitatively compared each other. The calculation results of CUPID code shows a good agreement with the experimental data. It is concluded that the CUPID code has capability to reproduce the turbulent flow behavior for the 2x2 rod bundle geometry.
박익규(I.K. Park),조형규(H.K. Cho),이재룡(J.R. Lee),김정우(J. Kim),윤한영(H.Y. Yoon),이희동(H.D. Lee),정재준(J.J. Jeong) 한국전산유체공학회 2011 한국전산유체공학회지 Vol.16 No.2
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.
CUPID 코드를 이용한 CANDU 감속재의 열-유동 예비해석
박상기(S.G. Park),이재룡(J.R. Lee),윤한영(H.Y. Yoon),정재준(J.J. Jeong) 한국전산유체공학회 2012 한국전산유체공학회 학술대회논문집 Vol.2012 No.11
The objectives of this study are to predict CANDU moderator temperatures by using the CUPID code and to validate the CUPID against STERN 2D experimental data. In this study, both single and two phase flows in the Calandria vessel were calculated by using the CUPID code. KAERI has been developing the CUPID Code. It adopts three-dimensional, transient, two-phase and three-field model, and includes various physical models and correlations of the interfacial mass, momentum and energy transfer for the closure relations of the two-fluid model. The CUPID code validated using the single-phase flow experimental data that were performed in the STERN Lab.