학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Improvement of Interfacial Heat Transfer Model and Correlations in SPACE Code | Sung Won Bae and Kyung Du Kim(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Validation of the TASS/SMR-S Code for the PRHRS Condensation Heat Transfer Model | In Sub Jun, Soo Hyoung Yang, and Young Jong Chung(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of a Novel Infrared-based Visualization Technique to Detect Liquid-gas Phase Dynamics on Boiling Surfaces | Hyungdae Kim(KHU) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | The Effect of a CANDU Fuel Bundle Geometry on Dryout Power | Jun Ho Bae and Joo-Hwan Park(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Evaluation of the PRHRS Performance Degradation due to Non-condensible Gas for the Small and Medium Reactor Using MARS-KS Code | Sook Kwan Kim and Suk Ku Sim(en2t) Ju Yeop Park, Kwang Won Seol, and Yong Ho Ryu(KINS) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Radionuclide Release after Channel Flow Blockage Accident in CANDU-6 Plant | Hoon Choi and Hwang-Yong Jun(KEPCO RI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Feasibility Study to Advanced Design Features of the APR1000 through CEA Ejection Accident Analysis | Yo-Han Kim, Chang Keun Yang, Hwan Soo Lee, and Sang Jun Ha(KEPCO RI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Case Study of PHWR ROP Thermal Hydraulic Calculation Methodology | Eui-Seung Ryu, Sung-Tae Yang, and Kyung-Ho Roh(KHNP) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis the PORV Accident for the Kori #2 Using SPACE Code | Bum-Soo Youn, Hwang-Yong Jun, Dong-Hyuk Lee, Se-Yun Kim, and Sang-Jun Ha(KEPCO RI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis of ATLAS 6-inch Cold Leg Break Simulation with MARS-KS Code | Seyun Kim, Hwang-Yong Jun, and Sang-Jun Ha(KEPCO RI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Simulation of the VISTA SG Heat Transfer Experiment Using MIDAS/SMR | Jong-Hwa Park, Dong-Ha Kim, Young-Jong Chung, and Sunhee-Park(KAERI) Seong-Won Cho(KORTIC) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | LOFT L9-3 ATWS Experiment Simulation Using the SPACE Code | Chang-Keun Yang, Dong-Hyuk Lee, Yo-Han Kim, and Sang-Jun Ha(KEPCO RI) Sung-Yull Hong(YU) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Numerical Simulation for a Core Simulator of ACOP | Jun Ho Bae, Dong Jin Euh, and Tae-Soon Kwon(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | CFD Analysis for the Variation of Flow Pattern between the Real Model with Holes and Simplified Model with Porous in Steam Generator | Y. G. KIM, Y. M. JEON, Y. M. BAE, Y. I. KIM, C. T. PARK, and S. CHOI(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Verification of FAST Code Using Method of Manufactured Solution | Hyuk Kwon, K. W. Seo, S. J. Kim, J. H. Cha, T. W. Kim, and D. H. Hwang(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
