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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) 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 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermal Hydraulic Models of THALES Code Jong Seon Lim, Kee Yil Nahm, and Shane Park(KNF) Dae Hyun Hwang(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of Power Pulse in Large LOCA Using the IST Code for CANDU6 NPP Park Dong Hwan and Kim Yun Ho(KEPRI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of the General Safety Requirements for New Innovative Reactors Sang-Kyu Ahn, Kju- Myeng Oh, and Chang-Ju Lee(KINS) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Trip and Control System Models in SPACE Code Eun Ju Lee, Chan Eok Park, and Gyu Cheon Lee(KOPEC) PDF보기 -
Last Modified : 1998-Autumn