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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Investigation of Characteristics of Impinging Jet for 1/5-Scale ECC Injection Byung Soo Shin, Yung Joo Ko, Hwang Bae, and Tae Soon Kwon(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) 1/5-Scale Air Water Test for ECC Bypass Byung Soo Shin, Hwang Bae, Yung Joo Ko, and Tae Soon Kwon(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Measurement Technique for Droplets During Reflood Byoung Jae Kim, Hyung Kyu Cho, and Sang Ki Moon(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Performance Comparison of Deflector and DVI+ Duct Tae-Soon Kwon, Seungtae Lee, and Chul-Hwa Song(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Study on Flooding Phenomenon Yong Jin Kim(KAIST) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Preliminary Study on the Propagation of RCP Pressure Perturbation into Reactor Vessel Downcomer In-Cheol Chu, Jung Taek Kim, Tae Soon Kwon, and Chul-Hwa Song(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Study of ECC Duct Bypass for Development of an Advanced DVI+ Seungtae Lee, Young Jung Yun, Dongjin Euh, and Tae-Soon Kwon(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Measurement of the Superheated Steam Temperature in a Post-CHF Dispersed Droplet Flow Regime Seok Cho, Sang-Ki Moon, Hyung-Kyu Cho, Young-Jung Yun, Jeong-Kuk Park, Chul-Hwa Song, and Won-Pil Ba PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) 3D Analysis of Cooling Performance with Loss of Offsite Power Using GOTIHIC Code Kyemin Oh and Gyunyoung Heo(KHU) Insik Na(ACT Co., Ltd.) Yujung Choi(KHNP) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Fretting Wear Experiments between the Same Alloy 690 Materials for Conservative Wear Evaluation of Steam Generator Tube Jeong-Keun Lee and Chi-Yong Park(KEPRI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Establishment of Advanced Technique for the Prediction of pH in the Sump Solution Hee Cheol Kim and Sang-Nyung Kim(KHU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of Generalized Correlation Equation for the Lacal Wall Shear Stress Yu Mi Jeon, Jun Ho Bae, and Joo Hwan Park(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Validation of the PRHRS Model in the TASS/SMR-S Code Kyungmin Kang, Soo Hyung Yang, Young-Jong Chung, and Won-Jae Lee(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary CFD Analyses on Debris Transport to ECCS Sump in Recirculation Mode for CANDU Type Plant, in Korea Byung Il KWON, Jong Uk KIM, and Jae Seon CHO(FNC Tech.,) Tae Keun PARK(KOPEC) Sang Won LEE and Hyeon PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Prediction of TASS/SMR-S Code for the Natural Circulation at VISTA Facility InJoon Hwang, Soo-Hyung Yang, Soo-Hyung Kim, Young-Jong Chung, and Won-Jae Lee(KAERI) PDF보기 -
Last Modified : 1998-Autumn