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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2006-Autumn 제5분과 : 원자력안전 Seawater Resistance Evaluation of Existing NPP Concrete Structures Using High-sulfate Resistance Portland Cement Yoon,Eui-Sik,Paek,Yong-Lak,Choi,Kang-Ryong,and Chung, Yun-Suk(KINS) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Suggestion to Evaluate Accurate Shear Capacity of Cast-in-place Anchor by ACI 349 Code J.B.Jang,K.M.Hwang,J.K.Kim,and K.J.Kwon(KEPRI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Multi-objective Optimization for Support Location of Reactor Head Lifting Structure Tae-Kyo Kang(KOPEC) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Thermal-hydraulic Performance of a Hybrid Vane and Split Vane in a PWR Fuel Assembly W.K.In,C.H.Shin,D.S.Oh,and T.H.Chun(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Comparison of Turbulence Models for Simulation of Flow Around an Orifice Flowmeter Seong Hoon Kim and Juhyeon Yoon(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Web-based, Interactive, Nuclear Reactor TransientAnalyzer Using LabVIEW and RELAP5 (ATHENA) K.D.Kim and B.D.Chung(KAERI)Rizwan-uddin(IllinoisUniv.) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 System Response Analysis of Rod Ejection Accidentfor APR1400 Using KNAP Hot Spot Model Yo-Han Kim,Sang-JunHa,and Hwang-Yong Jun(KEPRI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Simulation of a Natural Convection by the Hybrid Thermal Lattice Boltzmann Equation Seungyeob Ryu,HanokKang,Jaewang Seo,Juhyeon Yun,and Sung-Quun Zee(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Flow Behavior in the Steam Generator U-tubes of APR1400 During a Transient Operation Doo-Hyuk Kang,Seung-Wook Lee,and Bub-DongChung(KAPRI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Counter-current Experiments for the Direct ContactCondensation of Pure Steam on a Stratified Liquid ina Horizontal Pipe Hyun-Sik Park(KAERI)Sung-Won Choi(PurdueUniv.)Hee-Cheon No(KAIST) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Preliminary Study on the Development of MIDAS/GCR to Simulate the Plate-out Phenomenafrom a HTGR Jong-Hwa.Park,Dong-Ha. Kim,and Won-Jae.Lee(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 The Analysis of Uncontrolled CEA Bank Withdrawal from Low Power Accident for APR1400 Using KNAP Chang-Keun Yang,Yo-HanKim,and Sang-Jin Ha(KEPRI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Thermal-hydraulic Analysis of a Small Scale HighTemperature and High Pressure Gas Loop Dong Seok Oh,Sung DeokHong,Jong Ho Kim,ChanSoo Kim,and Yong WanKim(KAERI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 Development of the Interactive Model Between Component Cooling Water System and Containment Cooling System Using GOTHIC Choong Sup Byun,DongSoo Song,and HwangYong Jun(KEPRI) PDF보기 -
2006-Autumn 제5분과 : 원자력안전 APR1400 Complete Loss of Flow Accident Analysis Using KNAP Dong-Hyuk Lee,Yo-HanKim, and Sang-Jun Ha(KEPRI) PDF보기 -
Last Modified : 1998-Autumn