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