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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis of Flow Characteristics in a Fluidic Device for Design Optimization and RELAP5/MOD3.3 Code Validations with LBLOCA Using the New Pressure Loss Models Sang-Gyu Lim, Seok-Ho Lee, and Han-Gon Kim(KHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of the Coastdown Speed for a Canned Motor Pump Jin Seok Park, Suhn Choi, and Keung Koo Kim(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Study on the Feasibility of CHF Data Integration Ho-Young Park, KangHoon Kim, and Eung-Jun Park(KNF) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Implementation of a Second Order Interpolation Scheme for the Convective Terms of a Two-phase Flow Analysis Solver, CUPID H. K. Cho, I. K. Park, and J. J. Jeong(KAERI), H. D. Lee(KAIST) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Semi-implicit Numerical Method with a Symmetric Pressure Matrix for Multi-dimensional Two-phase Flows H. Y. Yoon, Y. I. Kim, Y. D. Hwang, and J. J. Jeong(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Boron Transport Model in SPACE Code Jong Cheol Park, Chan Eok Park, and Gyu Cheon Lee(KOPEC) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Convective Heat Transfer Correlation of a Supercritical CO2 with Vertical Downward Flow in Circular Tubes Tae Ho YOO(HNU), Hwan Yeol KIM and Yoon Yeong BAE(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Developmental Status of the Staggered Mesh Hydraulic Solver in SPACE Chan Eok Park, Sang Yong Lee, and Eun Ki Kim(KOPEC) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Status and Perspective of the Pre/Post Processing for Thermal-hydraulic Code Sang Yong Lee, Chan Eok Park, and Eun Ki Kim(KOPEC) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Alternative Method of Uncertainty Treatment in Safety Valve Test Tolerance Jong-Gwan Yoo and Jong-Woon Park(KHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Study on Developing Degradation Model for Nuclear Power Plants with Ageing Elements Affected on Operation Parameter Yong Won Choi, Sung Won Lim, and Un Chul Lee(SNU) Manwoong Kim, Kab Kim, and Yongho Ryu(KINS) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Review Guide for a Level-3 PSA of Nuclear Power Plants Jongtae Jeong(KAERI) Kyu-Myeng Oh, Sang-Kyu Ahn, and Chang-Ju Lee(KINS) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Application of HERA for a Qualitative Error Analysis of an Emergency Scenario Wondea Jung and Jinkyun Park(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Abnormal Signal Analysis for a 4~20mA Equivalent Circuit Regarded as High Temperature Accident Conditions Kil-Mo Koo, Yong-Mann Song, Kwang-Il Ahan, and Joon-Eon Yang(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Incorporation of Truncation Errors in Auxiliary Feed Water System PSA by CUTREE Dongil Lee and Nam Zin Cho(KAIST) PDF보기 -
Last Modified : 1998-Autumn