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국제학술발표회 논문집

No Conference Name Year Subject Area Title Author Paper File
391 MC2017 2017 General Reactor Analysis Methods and Applications Extended Radial Reflector Modeling Capabilities in MPACT S. Stimpson, B. Collins, A. Godfrey, F. Franceschini, D. Salazar(ORNL) PDF보기
392 MC2017 2017 Computational Fluid Dynamics CFD Simulation of a 61-pin Wire-wrapped Fuel Subassembly for Sodium Cooled Fast Reactor Jing Chen, Dalin Zhang, Xinan Wang, Suizheng Qiu, G.H. Su, Yapei Zhang (XJTU) PDF보기
393 MC2017 2017 Computational Fluid Dynamics Large Eddy Simulation of Turbulent Flows Using the CFD Code GASFLOW-MPI. Han Zhang, Jianjun Xiao, Thomas Jordan(KIT) PDF보기
394 MC2017 2017 Computational Fluid Dynamics CFD Modeling Of The 37 Rod Bundle Experiment V.Yu. Volkov, L.A. Golibrodo, A.A. Krutikov, O.V. Kudryavtsev, A.P. Skibin, L.L. Kobzar, D.A. Oleksyuk(Gidopress) PDF보기
395 MC2017 2017 Computational Fluid Dynamics Multiphase Turbulence Mechanisms Identification from Consistent Analysis of Direct Numerical Simulation Data B. Magolan, E. Baglietto, C. Brown, I.A. Bolotnov, G. Tryggvason, J. Lu(MIT) PDF보기
396 MC2017 2017 Computational Fluid Dynamics Multiscale simulation of Light Water reactor thermalhydraulics D. Bestion (CEA) PDF보기
397 MC2017 2017 Computational Fluid Dynamics Evaluating the Practicability of Multiphase CFD for BWR Fuel Assembly Analysis Su-Jong Yoon, Giulia Agostinelli, Emilio Baglietto (INL) PDF보기
398 MC2017 2017 Computational Fluid Dynamics Evaluation of a Hyperbolic Conservative Mixture Model for Thermal-Hydraulics Two-Phase Flows of Nuclear Reactors Dia Zeidan, Henrik Ström(GJU) PDF보기
399 MC2017 2017 Computational Fluid Dynamics Verification and Validation of CFD Simulations involving Twin Retangular Jets using Steady RANS in Star-CCM+ L. B. Carasik, Y. A. Hassan (TAMU) PDF보기
400 MC2017 2017 Computational Fluid Dynamics Identification of Vortical Flow Pattern inside PWR Fuel Assembly Gong Hee Lee, Ae Ju Cheong(KINS) PDF보기
401 MC2017 2017 Computational Nuclear Thermal-Hydraulics Investigation of Reverse Flow Restriction Device to Mitigate Fuel Dryout during BWR Loss of Coolant Accidents Majdi I. Radaideh, Tomasz Kozlowski, Yousef M. Farawila, Travis Mui (Illinois) PDF보기
402 MC2017 2017 Computational Nuclear Thermal-Hydraulics Transient Characteristic Analysis of Nuclear Metallic Fuel System Zhang Chi, Zhou Qi, Zhang Geng, Xia Zhaodong, Zhu Qingfu (CIAE) PDF보기
403 MC2017 2017 Computational Nuclear Thermal-Hydraulics Development of whole CORe Thermal Hydraulic analysis code CORTH Pan JunJie, Tang QiFen, Chai XiaoMing, Lu Wei, Liu Dong(NPIC) PDF보기
404 MC2017 2017 Computational Nuclear Thermal-Hydraulics Coupling FHR Core Design with Power Conversion System Zhiyao Xing, Eugene Shwageraus(Cambridge) PDF보기
405 MC2017 2017 Computational Nuclear Thermal-Hydraulics Extension of the Component Thermal-Hydraulics Analysis code CUPID toward Subchannel Scale Analysis of Rod Bundle Geometry under Isothermal Single and Two-phase Conditions Seok-Jong Yoon, Goon-Cherl Park, Hyoung-Kyu Cho(SNU) PDF보기
Last Modified : 2023.11.20