학술정보출판물

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국제학술발표회 논문집

No Conference Name Year Subject Area Title Author Paper File
331 MC2017 2017 Computational Fluid Dynamics Multiscale simulation of Light Water reactor thermalhydraulics D. Bestion (CEA) PDF보기
332 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
333 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
334 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
335 MC2017 2017 Computational Fluid Dynamics Identification of Vortical Flow Pattern inside PWR Fuel Assembly Gong Hee Lee, Ae Ju Cheong(KINS) PDF보기
336 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
337 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
338 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
339 MC2017 2017 Computational Nuclear Thermal-Hydraulics Coupling FHR Core Design with Power Conversion System Zhiyao Xing, Eugene Shwageraus(Cambridge) PDF보기
340 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
341 MC2017 2017 Computational Nuclear Thermal-Hydraulics Validation Of The SC-INT Code Using Experimental Data On Coolant Mixing In A 37-rod Fuel Assembly With Heat Exchange Intensifying Spacer Grids D.R. Kireeva, D.A. Oleksyuk (Kurchatov) PDF보기
342 MC2017 2017 Computational Nuclear Thermal-Hydraulics Solution Verification of CTF and CTF-R Using Isokinetic Advection Test Problems Nathan Porter, Maria Avramova, Vincent Mousseau(NCSU) PDF보기
343 MC2017 2017 Computational Nuclear Thermal-Hydraulics Development and Assessment of CTF for Pin-resolved BWR Modeling R. Salko, A. Wysocki, B. Collins, M. Avramova, C. Gosdin (ORNL) PDF보기
344 MC2017 2017 Computational Nuclear Thermal-Hydraulics Confirmation Of Wilks' Method With TRACE Modeling Of BWR Spray Cooling Travis Mui, Tomasz Kozlowski(Illinois) PDF보기
345 MC2017 2017 Computational Nuclear Thermal-Hydraulics Bifurcation Analysis of Pressure Drop Oscillations in Two-Phase Flow System Md Emadur Rahman, Munendra Pal Singh, Suneet Singh (IITB) PDF보기
Last Modified : 2019.11.27