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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2006-Spring 제5분과 원자력안전-안전현안 Validation of a CFD Code for Unsteady Flows with Cyclic boundary Conditions Jongtae Kim, Sang-Baik Kim, and Won-Jae Lee (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Small Break LOCA Analysis for Kori 1 in Operation Mode 3 and 4 Hong, Soon-Joon and Lee, Byung-Chul (FNC) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Improvement of the NSSS T/H Module ARTS for Enhancing the Simulation Fidelity of YGN #1/2 Simulator In Young Seo, Myung Soo Lee, and Yong Kwan Lee (KEPRI) Jae Seung Suh (ENESYS) Gyoo Dong Jeun (HYU) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 A CFD Analysis of the HANARO Irradiation Test Rigs for DUPIC Mini-elements Churl Yoon, Joo Hwan Park, Kwon Ho Kang, and Kee Chan Song (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Development of the T/H Model for Aged Core in Wolsong-1 NPP Kim Yun Ho, Choi Hoon, and Kim Yong Bae (KEPRI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Comparative Evaluation of Realistic and Deterministic Approach for Secondary System Piping Break Accidents Cheol Shin Lee, Shin Whan Kim, and Jong Tae Seo (KOPEC) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Assessment of a Cryogenic Cooling System Malfunctioning Accident in a CNS Jonghark Park and Kyehong Lee (KAERI) Donggil Hwang (Decon Eng.) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Modular Feedwater and Steam Lines Heat Transfer Effect on the Thermal Performance of a Once Through Steam Generator Jae-Kwang Seo, Han-Ok Kang, Young-In Kim, Juhyeon Yoon, and Keung-Ku Kim (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 APR1400 Steam Generator Tube Rupture Accident Analysis Using KNAP Jae-Hwa Koh, Yo-Han Kim, Dong-Hyuk Lee, and Chang-Kyung Sung (KEPRI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Analysis of Critical Flow Test Results for the Simulation of Loss of Coolant Accidents C. K. Park, H. S. Park, Y. J. Yoon, and C. H. Song (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 System Response Analysis of LOCV for APR1400 Using KNAP Yo-Han Kim, Chang-Kyung Sung, and Hwan-Yong Jun (KEPRI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 The Analysis of Control Rod Drop Accident for APR1400 Using KNAP Chang-Keun Yang, Yo-Han Kim, and Chang-Kyung Sung (KEPRI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Flow Distribution in the Curved Narrow Channels of a Tubular Fuel Jonghark Park, Heetaek Chae, Cheol Park, and Heonil Kim (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 An Analysis of Heat Transfer and Subcooled Boiling in the Mixing Vane Grid Seung Geun Yang, Hyun Mi Hong, Kang Hoon Kim, Hong Ju Kim, Sun Tack Hwang, and Eung Jun Park (KNFC) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Prediction of the Inlet Nozzle Velocity Profiles for the CANDU-6 Moderator Analysis Churl Yoon and Joo Hwan Park (KAERI) PDF보기 -
Last Modified : 1998-Autumn