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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) 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 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of Reactor Trip Database Management System Tae-Young Shin, Hyuk-Soon Lim, and Byung-Sik Lee(KHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Estimation of Internal Flooding Frequency for Screening Analysis of Flooding PSA by Using the Latest Generic Data and the Korean Plant Operation Data Sun Yeong Choi and Joon-Eon Yang(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Study on the Technical Acceptability of PRA for Future Plants Kju-Myeng Oh, Sang-Kyu Ahn, and Chang-Ju Lee(KINS) Jong-Tae Jeong(KAERI) PDF보기 -
Last Modified : 1998-Autumn