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) | Conceptual Design Study of the RCP Test Loop | Won-Myung Choung, Chang-Hwan Chung, Heung-June Chung, Jin-Seok Park, Ji-Won Yeo, Tae-Soon Kwon, Chan | PDF보기 | - | ||
2008-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Basic Study for Active Nucleation Site Density Evaluation in Subcooled Flow Boiling | In-Cheol Chu and Chul-Hwa Song (KAERI) | PDF보기 | - | ||
2008-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis of a CHF Disappearing Phenomenon and the Prediction Correlations for the Threshold Pressures | S. D. Hong and W. J. Lee (KAERI), G. C. Park (SNU) | PDF보기 | - | ||
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 | - |
Last Modified : 1998-Autumn