-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Assessment of the KAERI 6x6 Reflood Experiment for the SPACE Code Using General Wall Heat Transfer Models Sang-Ki Moon, Jungwoo Kim, Kyung-Doo Kim, Ki-Yong Choi, Hyun-Sik Park, and Seok Cho(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluating the Break Flow for the 100% DVI Line Break Accident of ATLAS Using the RELAP5/MOD3.3 Code Suk-Ho Lee, Sung-Chang You, and Han-Gon Kim(KHNP) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Case Study of MATRA-S for PNL 7x7 Rod Bundle Blockage Test - I. Subchannel Analysis Kyong-Won Seo and Dae-Hyun Hwang(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Core Heat Transfer Model Validation of the TASS/SMR-S Code Using the Bennett s Test In Sub Jun, Kyu Hwan Bae, Young Jong Chung, and Won Jae Lee(KAERI) In Sik Na(ACT Co., Ltd.) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) SPACE Code Development and Assessment Plans Chang-Keun Yang, Dong-Hyuk Lee, Yo-Han Kim, and Sang-Jun Ha(KEPCO RI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Verification of the Core Side Pressure Drop Calculation Sub-routine Jeong-hun Cha, Kyong-Won Seo, Hyuk Kwon, Teawoo Kim, and Dae-Hyun Hwang(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An ATWS Analysis with a Realistic Evaluation Methodology Min Shin Jung, Gyu Cheon Lee, and Eun Kee Kim(KEPCO E&C) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Gap Conductance Model Validation in the TASS/SMR-S Code Using MARS Code Sang-Jun Ahn, Soo Hyung Yang, Young-Jong Chung, and Won-Jae Lee(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of Heat Load to Moderator in Large LOCA for CANDU NPP Kim Yun Ho(KEPCO RI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preparation of Input Deck Using MULTID Component to Model 3-dimensional Reactor Pressure Vessel for KORI 3&4 Doo-Hyuk Kang, Jae-Seung Suh, Kyung-Chul Seo, Yeon-Sik Cho, and Ji-Hoon Park(SENTECH) Seung-Hoon Ahn PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermalhydraulic Response of CANDU6 in the End Fitting Failure Event Kwangho Lee and Hoon Choi(KEPCO RI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Assessment of the Reflood Heat Transfer Models for the SPACE Code Jungwoo Kim, Sang-Ki Moon, Ki-Yong Choi, Hyun-Sik Park, and Kyung-Doo Kim(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Detached-Eddy Simulation of a Fluidic Device for a Prediction of Pressure Loss Characteristics in a Low Flow Mode Sang-Gyu Lim, Suk-Ho Lee, and Han-Gon Kim(KHNP) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Feasibility Study on the Steady State Initialization of SPACE Code Chansu Jang and Kilsup Um(KEPCO NF) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Improvement of SPACE Momentum Equation to Mitigate Non-physical Pressure Solution Chan Eok Park, Jung Yoon, Sang Yong Lee, and Eun Kee Kim(KEPCO E&C) PDF보기 -
Last Modified : 1998-Autumn