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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Preliminary Study for Reactor Kinetics Modeling Seung Chan LEE(KHNP) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Wall-modelled LES of the Turbulent Flow in a Nuclear Fuel Rod Bundle Ye Jun Lee and Jungwoo Kim(SEOULTEC) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) CFD Modeling for Reactor Coolant System Natural Circulation Applied with a Tube Simplification Technique Dae Kyung Choi and Choengryul Choi(Elsoltec), Kukhee Lim and Yong Jin Cho(KINS) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Preliminary CFD Study of Pressure Drop in Helical Tube Steam Generator for SMR Application Doh Hyeon Kim and Jeong Ik Lee(KAIST) PDF보기 -
2022-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:00 로비 (3F) Implementation of New Condensation Model into the CAP Code Kum Ho Han, Jehee Lee, Yeon Jun Choo, and Soon Joon Hong(FNC Tech.) PDF보기 -
Last Modified : 1998-Autumn