학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A New Correlation for Counter-current Flow Limited CHF in Narrow Rectangular Channels | Ju Hyung Lee and Soon Heung Chang(KAIST) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Evaluation on the Conservative Critical Flow Model in SPACE Code Using Marviken Test | Suk-Ho Lee and Han-Gon Kim(KHNP) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Implicit Safety Injection Tank Model of the SPACE Code and Its Validation | Dong Eun Kim, Il Soon Park, Chan Eok Park, and Jong Joo Sohn(KEPCO E&C) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of a Two-dimensional Heat Structure Model in SPACE Code | Jungwoo Kim, Seung-Wook Lee, and Kyung Doo Kim(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Fuel Model Validation in the TASS/SMR-S Code by Comparing with Experimental Results | Sang-Jun Ahn, Soo Hyung Yang, Young-Jong Chung, and Won-Jae Lee(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Drag Models for Annular Flow in SPACE Code | Byoung Jae Kim and Kyung Doo Kim(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Evaluation of RCP Model for TASS/SMR-S Code | Sung Won Lim, Young Jong Chung, and Won Jae Lee(KAERI) | PDF보기 | - | ||
| 2011-Spring | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experimental Validation of TASS/SMR-S Critical Flow Model for the ntegral Reactor SMART | Si Won Seo, In Sik Ra, and Kun Yeup Kim(ACT Co., Ltd) Youngjong Chung(KAERI) | PDF보기 | - | ||
| 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 | - |
Last Modified : 1998-Autumn
