-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2006-Autumn 제5분과 : 원자력안전 Improved Methodology of LOCA M/E ReleaseAnalysis for OPR1000 Jeung Hyo Song,Taek MoKim,Cheol Woo Kim,and J.T.Seo(KOPEC) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Improved Methodology of MSLB M/E ReleaseAnalysis for OPR1000 Seok Jeong Park,CheolWoo Kim,and Jong TaeSeo(KOPEC) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 SBLOCA Mass and Energy Release Analysis for Kori3&4 EQ T.M.Kim,C.W.Kim,K.S.Han,J.H.Song,and J.T.Seo(KOPEC)D.S.Song(KEPRI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Containment Response Analysis for Equipment Qualification of Kori Nuclear Power Plant Unit 3 and 4 Choong Sup Byun,DongSoo Song,and HwangYong Jun(KEPRI)Kwi Hyun Seo and WanJung Song(ENERGEO) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Preliminary Analyses on the ATWS Events for OPR1000 Using RETRAN-3D Code Sang Won Lee and YeonKyoung Bae(KHNP) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Assessment of MEDUSA Code with Turbine Trip & Natural Circulation Test of YGN Unit 6 Jong Cheol Park,ChanEok Park,and Jong TaeSeo(KOPEC) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Analysis of LOFT Experiments L6-1 and L6-5 Using MEDUSA Code Myung Taek Oh,Chan EokPark,Sang Yong Lee,and Jong Tae Seo(KOPEC) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Safety Evaluation of Low-temperature Overpressurization Events for Yonggwang Units 1&2 Jongbeom Lee(KHNP) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 An Approach for Quantifying Safety Margins in Nuclear Power Plants Huichang Yang and JeongIck Yun(ENESYS)Jeong Seuk Park and JuYeop Park(KINS) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Head Loss Coefficient Evaluation Based on CFD Analysis for PWR Downcomer and Lower Plenum Ji Hwan Jeong and JongPil Park(PNU)Byoung Sub Han(ENESYS) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Cooling Analysis of Spent Fuel Pool with a CFDMethod H.C.Jang,B.R.Jung,and J.K.Hwang(KOPEC) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Analysis of SBLOCA in SMART-P Using RELAP5/SMRCode Su Hyun Hwang,SoonJoon Hong,and ByungChul Lee (FNC)Young Seok Bang,ByungGil Huh,and Kwang-WonSeul(KI PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Components Effects for the Performance of thePassive Residual Heat Removal System of an Advanced Integral Type Reactor Hyun-Sik Park,Ki-YongChoi,Sung-Jae Yi,and Moon-Ki Chung(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Development of Coupled Interface System Betweenthe FADAS Code and a Source-term Evaluation Code XSOR for CANDU Reactors Han Seong Son and DeokYong Song(ENESYS)Manwoong Kim,ShinHyeong Ki,Sang-Kyu Lee,and Hyun-Koon Kim(KIN PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Application of Subcooled Boiling Model to Thermal-hydraulic Analysis Inside a CANDU-6 Fuel Channel Manwoong Kim,Sang KyuLee,and Hyun Koon Kim(KINS)Jin Bok Yu(ATES) PDF보기 -
Last Modified : 1998-Autumn