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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) 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 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Recent Improvements of MARS-KS Code Kyung-Won Lee, Andong Shin, Aeju Cheong, Min Ki Cho, Jae Soon Kim, and Kwang Won Seul(KINS), Bub Dong Chung(FNC Tech.), Seung Wook Lee and Sung Won Bae(KAERI), Jae Seung Suh(SENTECH), Jae Jun Jeong(PNU) PDF보기 -
2022-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Establishment of Evaluation Method for Integrity of Fuel Assembly in PGSFR, and Preliminary Analysis SeoYoon Choi and Jaeho Jeong(Gachon Univ.), HyungKyu Kim(KAERI) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Estimation of Conditional Exceedance Probability for LBLOCA using Monte-Carlo and Alternative Method Dong Gu Kang, Do Kyun Lim, Il Suk Lee, Deog Yeon Oh, and Yong Seok Choi(KINS) PDF보기 PPT보기
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Distribution Estimation for the Critical Size of Dispersed Fuel Particle Result from LBLOCA MIN KI CHO and JOOSUK LEE(KINS) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Effect of CRUD Layer on the Heat Transfer in the Reflood Situation using the SPACE Donggyun Seo and Hyungdae Kim(KHU), Youngjae Park(FNC Tech.), Boungjae Kim(CNU) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Improvement Methodology of Constitutive Equations in Safety Analysis Code using Integral Effect Test Data ChoHwan Oh, Doh Hyeon Kim, and Jeong Ik Lee(KAIST) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Feasibility Estimation of Development of Real-time Interactive Nuclear Accident Simulation Using Supervised Learning Seok Ho Song, Yeon Ha Lee, and Jeong Ik Lee(KAIST) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Simulation of Dispersal of Fuel Particles with STAR-CCM+ Haeyong Jeong and Jaegon Ryu(Sejong Univ.) PDF보기 PPT보기
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Preliminary Development of Alkali Metal Heat Pipe Code for Microreactor Transient Analysis Yeong Hun Lee and Hyoung Kyu Cho(SNU) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Proposal on Operating Modes of TES Test Facility using Sodium Hyeonil Kim, Jung Yoon, Yong-Hoon Shin, and Jewhan Lee(KAERI) PDF보기 PPT보기
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Investigation of Computational Modeling of Helical Once-Through Steam Generator for Integrated System Analysis Youngsuk Bang, KeonYeop Kim, So Eun Shin, Yeon Jun Choo, and Sung Kyun Zee(FNC Tech.) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) A Conceptual Design of Supercritical CO2 Brayton Cycle for a Small Modular Molten Salt Reactor Sunghyun Yoo, Wonkoo Lee, and Kwon-Yeong Lee(HGU) PDF보기 PPT보기
Last Modified : 1998-Autumn