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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2006-Autumn 제5분과 : 원자력안전 Development of an Auto-validation Program for MARS Code Assessments Young Jin Lee and Bub-Dong Chung(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 A Study on the Maintenance Effectiveness Assessment for Active Components Woo Sang Lim and Seung Jong Oh(KHNP) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 MELCOR 1.8.5 Sensitivity Study of Molten CoreConcrete Interaction Experiment, SWICCS-1, 2 and 3 Yong Jin Cho and Nam Duk Suh(KINS) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 An Evaluation of a Coolant Injection into the In-vessel with a RCS Depressurization During the Total Loss of Feed Water in OPR1000 Rae-Joon Park,Sang-BailKim,and Hee-Dong Kim(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 The Effects of Mitigative Strategies on SBO Severe Accidents in the KSNP Soo Yong Park and DongHa Kim(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Performance Experiment of the Quenching Mesh a tHigh Velocity Flame S.W.Hong,J.H.Song,and H.D.Kim(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 A 1STStep Integration of the Restructured MELCOR for the MIDAS Computer Code S.H.Park and D.H.Kim(KAERI)S.W.Cho(KRTIC) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 A MARS and MIDAS Linked Accident Simulation forLarge LOCA in APR1400 Young Choi,K.R.Kim,D.H.Kim,and B.D.Chung(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Assessment on the Success Criteria and the Human Error Probability of the Power Uprated Plant Yong-Suk Lee(FNC)Eun-Chan Lee and Keun-Sung Lee(KHNP) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Calculation of Activation Energy by OIT Method forAging Evaluation of NPP Cable Kyung-Heun Park,Jong-Seog Kim,and Bok-GeeCho(KEPRI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Analysis of the Unexpected HANARO Trip History(1996~2005) ho-young Choi,choong-sung Lee,and guk-hoonAhn(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Development of Review Guidelines and Regulatory Review System for PWR Power Uprates Byung Gi Park and ByungChul Lee(FNC)Jong Seuk Park and Hun-Joo Lee(KINS) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Finite Element Analysis for Feed-water Nozzle of PWR Steam Generator by Stress Analysis Code 3G Jin H.Choi and S.N.Choi(KEPRI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Mode Identification of Guided Waves in a Curved Pipe Heung-Seop Eom,Sa-HoeLim,and Jae-Hee Kim(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Application of a Physical Protection to HANARO Jeong-Soo Ryu,CheolPark,Yeong-Garp Cho,Jung-Hee Lee,and Hoan-Sung Jung(KAERI) PDF보기 -
Last Modified : 1998-Autumn