학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Numerical Predictions of Flow Characteristics in a 90 Degree Bended Upward Elbow Located at the Downstream Region of a Flow Control Valve(Butterfly Valve) | Se Youl Won,Young SheopPark,Yun Jung Kim,and Seung Jong Oh(KHNP) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Independent Best Estimate Calculation and Uncertainty Evaluation of LBLOCA in KSNP | Yong Won Choi,Jun SooYoo,Chang Hwan Park,and Un Chul Lee(SNU) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Effectiveness of ECI in Very Small LOCA for Wolsong-1 NPP | Kin Yun Ho,Choi Hoon,and Kim Yong Bae(KEPRI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Effect of Longitudinal Pitch on the Convection Heat Transfer from the Tube Banks in Crossflow | Tae-Wan Kim,Dae-HyunHwang,Chung-Chan Lee,and Keung-Ku Kim(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | A Development of Web-based Application Programfor Motor-operated Valve Periodic Verification | Shinchel Kang,SungkeunPark,and Dohwan Lee(KEPRI)Yonghyun Lee(OpenSystem Service Co.) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Development of an Analysis Method for the SG Cassette Module Pipe Break Accident Analysis of anIntegral Type Reactor | H.K.Kim,S.H.Kim,H.C.Kim,Y.J.Chung,and S.Q.Zee(KAERI)H.S.Kim(CNU) | PDF보기 | - |
Last Modified : 1998-Autumn
