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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2022-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 10:00 606호 (6F) Gas Stratification of the Steam-air-helium Mixture Under Condensing Condition for Steady and Transient States Il Woong Park(Inha Univ.), Jia Yu and Yeon-Gun Lee(JNU) PDF보기 -
2022-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 10:20 606호 (6F) Preliminary Experiments of Large-scale Water Heat Pipe as Passive Cooling System in Nuclear Power Plants Ye Yeong Park and In Cheol Bang(UNIST) PDF보기 -
2022-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 11:00 606호 (6F) Experimental Investigation of Overfilled Sodium Heat Pipe with Different Orientation Dong Hun Lee and In Cheol Bang(UNIST) PDF보기 -
2022-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 11:20 606호 (6F) Realization of Thermocline for Thermal Energy Storage Study Using a Copper-sulfate Electroplating System Min-Ju Kim, Jeong-Won Han, and Bum-Jin Chung(KHU) PDF보기 PPT보기
2022-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 11:40 606호 (6F) Experimental study on the Station Block Out (SBO) Accompanied by a Small Break Loss of Coolant Accident (SBLOCA) Yusun Park, Byoung Uhn Bae, Jong Rok Kim, Jae Bong Lee, Seok Cho, Nam Hyun Choi, and Kyoung Ho Kang(KAERI) PDF보기 -
2022-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 12:00 606호 (6F) Fluid-to-Fluid Scaling Design for Integral Effect Test Facility of OPR1000 Using R134a Do Yeong Lim and In Cheol Bang(UNIST) PDF보기 -
2022-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 09:00 607호 (6F) Dynamic Modeling and Transient Analysis of a 5 × 5 Node Array in Solid Oxide Electrolysis Cell Using Quasi-3D Approach Jiwon Ahn and Hyoung Kyu Cho (SNU), Byung Ha Park and Chan-Soo Kim(KAERI) PDF보기 -
2022-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 09:20 607호 (6F) CFD Analysis of Subcooled Boiling Phenomena in the crud DeposItion Simulator for Nuclear energY (DISNY) Hyeon Ji Kim, Ji Yong Kim, and In Cheol Bang(UNIST) PDF보기 -
2022-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 09:40 607호 (6F) Inverted Core Flow Blockage Analysis in Micro-Marine Lead Cooled Fast Reactor Joo Hyung Seo and In Cheol Bang(UNIST) PDF보기 -
2022-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 10:00 607호 (6F) Flow Boiling CHF Model Development in Downward Facing Curved Rectangular Channel Under Almost Saturated Condition: Focus on Void Fraction Jun Yeong Jung, Min Suk Lee, and Yong Hoon Jeong(KAIST), Jung Hyun Song(SEC) PDF보기 -
2022-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 10:20 607호 (6F) Thermal Analysis of the CANDU Spent Fuel Storage Silo Tae Gang Lee and Jae Jun Jeong(PNU), Yong Deog Kim, Tae Hyeon Kim, and Tae Hyung Na(KHNP) PDF보기 -
2022-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 11:00 607호 (6F) Multiphysics Analysis of CEA Withdrawal at Power for the Korean APR1400 Reactor Jan Hruskovic and Aya Diab(KINGS) PDF보기 PPT보기
2022-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 11:20 607호 (6F) The Validation of the Coupled CUPID/FRAPTRAN Code using HALDEN and ICARUS Experiments Ik Kyu Park, Hyo Chan Kim, Sung Uk Lee, and Han Young Yoon(KAERI) PDF보기 -
2022-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 11:40 607호 (6F) Assessment of CUPID code for Multi-dimensional LOCA Analysis of NuScale Yun-Je Cho, Seong-Jun Lee, and Han-Young Yoon(KAERI) PDF보기 -
2022-Autumn 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 10.21(Fri) 09:00 607호 (6F) An Application of Data Assimilation to Improve the Prediction of the Reflood Tests Tiep NguyenHuu and Jeong Hae-Yong(Sejong Univ.), Kim Kyung-Doo(KAERI) PDF보기 PPT보기
Last Modified : 1998-Autumn