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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 11:00 203 (2F) Preliminary Experiment for Validation of Fission Product Flotation System in Passive Molten Salt Fast Reactor Yun Sik Cho, Hyo Jun Ahn, Do Won Lee, and Sung Joong Kim(HYU) PDF보기 -
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 11:20 203 (2F) Parametric Study of Hydraulic Performance of Flow with Helical Cruciform Fuel for LWRs Hyeongi Moon and Minseop Song(HYU) PDF보기 -
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 11:40 203 (2F) Modeling of Dynamic Response of Passive ECCS Valves Using MARS-KS Code in Support of i-SMR Young Seok Bang, Youngjae Park, and You Cho Choi(FNC Tech.) PDF보기 -
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 12:00 203 (2F) Thermal Analysis of the KRUSTY Experiment Using OpenFOAM-PRAGMA Coupled Code with Heat Pipe Thermal Analysis Module Myung Jin Jeong, Jaeuk Im, San Lee, and Hyoung Kyu Cho(SNU) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 09:00 202B (2F) A Mass and Energy Release Analysis of Postulated Main Steam Line Break Accidents on APR1000 Using KIMERA Methodology Jisu Kim, Sung Yong Kim, Seng Ho Jee, Chan Eok Park, Min Shin Jung, Eun Ju Lee, and Seok Jeong Park(KEPCO E&C) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 09:20 202B (2F) CFD Investigation of a MONJU 169-Pin Wire-Wrapped Fuel Assembly Experiment Seongchul Park and Jae-Ho Jeong(Gachon Univ.) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 09:40 202B (2F) Effect of Asymmetric Inlet Mass Flow Conditions on Flow Behavior Inside Subchannel of a 6×12 Rod Bundle Jun Yeong Jung, Seok Kim, and Hae-Seob Choi(KAERI) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 10:00 202B (2F) Evaluation of Condensation Models for the Outer Wall under Pure Steam Condition Dongwon Jeong and Byongjo Yun(Pusan National Univ.), Jinhoon Kang(KIMM), SangGyun Nam(FNC Tech.) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 10:20 202B (2F) Experimental Investigation on Wall Friction Factor in a Vertical Annulus Channel under Natural Circulation \'Water Flow Conditions Seongbae Park, Youngchang Ko, and Byongjo Yun(Pusan National Univ.) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 11:00 202B (2F) Investigation of Thermal Hydraulic Characteristics of PCCS According to the Containment Size Sang Gyun Nam, Youngjae Park, Jehee Lee, Jungjin Bang, and SeongSu Jeon(FNC Tech.) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 11:20 202B (2F) Modeling Steam Condensation on Passive Heat Sinks within Containment for Realistic Analysis of Heat Removal Behavior Jia Yu and Yeon-Gun Lee(Sejong Univ.) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 11:40 202B (2F) Preliminary CFD Analysis of Spreading and Solidification of FLiNaK and KCl-UCl3 Ye Hwan Chun, Jin Ho Song, Yun Sik Cho, Juhyeong Lee, Won Jun Choi, Jihun Im, and Sung Joong Kim(HYU), Sang Mo An and Sung-Il Kim(KAERI) PDF보기 -
2024-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 12:00 202B (2F) Validation of RV Model in CUPID Code Against a Rod Bundle Test, SIRIUS-3D, and Design of a New Rod Bundle Test Byong Guk Jeon, Jae Ryong Lee, Sang-Ki Moon, HaeSeop Choi, and Seok Kim(KAERI), Hyungmin Park(SNU) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 09:00 203 (2F) Calibration of Fuel Assembly Mockup of Advanced Research Reactor Taeil Kim, Yohan Lee, Donkoan Hwang, WooHyun Jung, Nakjun Choi, and HangJin Jo(POSTECH), Jonghark Park, Hyung Min Son, Huiyung Kim, Kiwon Song(KAERI) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 09:20 203 (2F) Numerical Simulation for ROCOM PTS Test using Generalized k-ω Turbulence Model Dong-Hyeon Choi and Yoon-Suk Chang(KHU) PDF보기 -
Last Modified : 1998-Autumn