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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Numerical Study on the Effect of an Inlet Orifice Hole Diameter on the Flow Characteristics Inside the Multi-stage Orifice Gong-hee Lee and June-ho Bae(KINS) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Validation Calculation of Reflooding Tests Using TRACE Code Seon Oh YU and Kyung Won LEE(KINS) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Study on the Wall Heat Transfer of Condensation in the Presence of NC Gases Jong Hyuk Lee and Kwi Seok Ha(KAERI) PDF보기 PPT보기
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Validation of the Motion Model in MARS-KS for Gravity Driven Injection Moonhee Choi, Hyungjoo Seo, and Hyoung Kyu Cho(SNU) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Improvement of Well-Posedness of SPACE Code Using Artificial Phase Change and Viscosity Byoung Jae Kim(CNU), Seung Wook Lee(KAERI) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) CFD Simulation of Subcooled Boiling Flow Sung Gil Shin, Soyoung Lee, and Jeong Ik Lee(KAIST) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Changes in Hydraulic Characteristics of APR Type Core Simulators in Different Simulation Conditions Won Man Park, Sung Man Son, Dae Kyung Choi, and Choengryul Choi(Elsoltec), Sang-Gyu Lim(KHNP) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Analysis of the Small Steam Leaks by Upstream Pressure Conditions Dae Kyung Choi, Won Man Park , Sung Man Son, and Choengryul Choi(Elsoltec), Woo-Shik Kim, Tae-Soon Kwon, and Dong-Jin Euh(KAERI) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Analysis of Single- and Two-phase Pressure Drop using SPACE Youngjae Park, Kum Ho Han, Jehee Lee, Jae-Ho Bae, SeongSu Jeon, and SoonJoon Hong(FNC Tech.), Do-Hyun Hwang(KHNP) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Validation of MARS-KS Code for Critical Heat Flux on a Single Heater Rod under Inclined Condition Yujeong Ko and Hyoung Kyu Cho(SNU) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Implementation of Enthalpy-Porosity Methodology in OpenFOAM for Validation of LIVE L7V and L7W Tests Seokwon Whang and Hyun Sun Park(SNU), Kukhee Lim(KINS) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Modeling of Steam Power Conversion System for APR1400 using MARS-KS Seongsu Jeon, Jungjin Bang, Dongyoung Lee, Youngseok Bang, Bubdong Chung, and Youngsuk Bang(FNC Tech.) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Investigation of Natural Circulation Instability for Inclined One-loop with Single-phase in MARS-KS Ju Hun Jeong, Ji Yong Kim, and In Cheol Bang(UNIST) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Influence of Rolling Motion on the Subchannel Analysis of Two-Phase Flows Dae-Hyun Hwang and Seong-Jin Kim(KAERI) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Investigation of Natural Convection Thermal Characteristics of BALI Experiment through Eulerian Computational Fluid Dynamics code and Comparison with Lagrangian code Hyeongi Moon and Jaeho Jeong(Gachon Univ.), Sohyun Park(Kim See Darl), Eungsoo Kim(SNU) PDF보기 -
Last Modified : 1998-Autumn