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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a CANDU Fuel Channel Model to Assess the Effect of a Pressure Tube Creep on the Safety Related Paramters Under a Stratified Two-Phase Flow Bo Wook Rhee, Gyu-Hong Roh, Hyung Tae Kim, and Joo Hwan Park (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Wrapper Object, TRelap, for RELAP5 Code for Use in Object Oriented Programs Young Jin Lee (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary CFD Analysis on Debris Transport to ECCS Sump in Recirculation Mode for Kori Unit 3 Su Won LEE, Kyung Jin LEE, and Soon Joon HONG (FNC), Sung Bok LEE and Hyeong Taek KIM (KHNP) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Multi-dimensional Analysis for Upper Plenum Injection Using MARS-KS Code Kyung Won Lee, Yong Jin Cho, and Seung Hoon Ahn (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Effect of TBS LOCA on the SIS Design for OPR1000 Byung Heon Hwang, Cheol Woo Kim, and Eun Kee Kim (KOPEC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Temperature Distribution Analysis for Monitoring Sample in Reactor Using FEM and FDM Method Chang-Keun Yang and Yohan Kim (KEPRI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Mesh Handling System for the SPACE Pilot Code Je. Woo. Cho, C. E. Park, and S. Y. Lee (KOPEC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Comparative Analysis for Control Rod Drop Accident in WH and CE Type Chang-Keun Yang, Yo-Han Kim, and Jun-Sang Ha (KEPRI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Steady-State Calculation of RD-14M Small Break LOCA Experiments by CATHENA Code Hyoung Tae Kim, Joo Hwan Park, and Sang Baik Kim (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Validation Region of the Boussinesq Approximation for Nuclear Reactor Operation and Atmospheric Pressure Conditions Hyuk kwon, K. W. Seo, and D. H. Hwang (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Validation of the Edwards Pipe Blowdown Experiment in the TASS/SMR Code See Darl Kim, S. H. Kim, G. H. Lee, and Young-Jong Chung (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Computational Analysis of Supercritical Carbon Dioxide Gas Turbine for Liquid Metal Cooled Reactor Wi S. Jeong and Kune Y. Suh (SNU) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Numerical Analysis of Thermohydrodynamics Interfacing Supercritical Fluid and Liquid Metal Jong H. Jung (PHILOSOPHIA), Wi S. Jung and Kune Y. Suh (SNU) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Uncertainty Test for the MAAP Computer Code S. H. Park, Y. M. Song, S. Y. Park, K. I. Ahn, K. R. Kim, and Y. J. Lee (KAERI) PDF보기 -
2008-Autumn 제 6 분과 : 방사선 이용 및 방호 (Radiation Utilization and Protection) An Evaluation of Characteristic X-ray Beam Source for X-ray Inspection System Using Monte Carlo Method Hwan Soo LEE, kyung-O KIM, Soon Young KIM, and Jong Kyung KIM (HYU) PDF보기 -
Last Modified : 1998-Autumn