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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) Evaluation of Fire Resistance on Fire Wall in Kori NPP 1 Wan-Yeong Koh, O-Hyun Keum, and Soo-Hyun Ryu(KINS) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of Boric Acid Precipitation Reflecting System Effects in Post LOCA Long-term Cooling Chang Hyun Kim and Sang Yeol Kim(KHNP) Jong Cheol Park(KOPEC) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Study on Natural Circulation in REX-10 Test Facility Byeong-ill Jang, Hyeong-Min Joo, Sun-Do Choi, and Gyoo-Dong Jeun(HYU), Moo-Hwan Kim(POSTECH) PDF보기 -
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 -
Last Modified : 1998-Autumn