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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Assessment of Post-accident Chemical Effects in Containment Sump Yu Jung CHOI, Snag Woo LEE, and Hyeong Teak KIM(KHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Review on ROP Update Methodology for CANDU-6 Plant Hoon Choi and Yong-Bae Kim(KEPRI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermalhydraulic Characteristics for Wolsung-1 after Retubing Jun Ho Bae and Joo Hwan Park(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Application of GEMINI2 Code to Develop the Sacrificial Concrete for the Core-catcher Experiment by KAERI Jong-Hwa Park, Jong-Hwan Kim, Byung-Tae Min, Hwan Yeol Kim, and Seong Wan Hong(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Estimation of the Gaseous Iodine Concentration in the Containment of Phebus FPT-1 Using MELCOR1.8.5 with a Revised Organic Iodide Model Jong-Hwa Park, Hee-Dong kim, and Seong Wan Hong(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Heat Loss Evaluation of the ATLAS Facility Seok Cho, Hyun-Sik Park, Ki-Yong Choi, Kyoung-Ho Kang, Yeon-Sik Kim, and Won-Pil Baek(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Hydrogen Safety Analysis of the OPR1000 Nuclear Power Plant during a Severe Accident by a Small-break Loss of Coolant Jongtae Kim, Soo-Yong Park, Kwang-Soon Ha, Seong-Wan Hong, and Sang-Baik Kim(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Flow Analysis in the Helical Wire Inserted Tube Using CFD Code Yusun Park and Soon Heung Chang(KAIST) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Effects of the Inclination Angle on Pool Boiling Heat Transfer in an Annulus Myeong-Gie Kang(ANU) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Experimental Study of the Post-CHF Phenomena on Flow-boiling of R-134a in an Annulus Geometry Kwi Lim Lee(KAERI), Soon Heung Chang(KAIST) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) The LBLOCA Analysis for APR1400 Power Plants Applying KREM with RELAP5/MOD3.3 Code Jae-Hoon Lee, Jae-Hoon Jeong, Woochong Chon, and Dong-Uk Choi(KNF) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation about Validity of the Passive Containment Cooling System Using Multi-pod Heat Pipe Hyun-Woo Lee and Sang-Nyung Kim(KHU) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermal Margin Budget of a Simplified Core Thermal-hydraulic Code for OPR1000 Wang-Kee In and Tae-Hyun Chun(KAERI) Jong-Sik Bae(Doosan Haevy Co., Ltd.) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Feasibility Study on Passive Auxiliary Feedwater System in Loss of Condenser Vacuum Accident Soon Joon Hong and Byung Chul Lee(FNC Tech.) Jong Cheon and Han Gon Kim(NHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS Assessment on Gravity Reflood Behavior in FLECHT-SEASET 33338 Test Dong Gu Kang, Seung Hoon Ahn, and Yong Jin Cho(KINS) PDF보기 -
Last Modified : 1998-Autumn