학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Application of the CUPID Code for the Simulation of Multi-dimensional Thermal Hydraulic Phenomena in Advanced Power Reactors | Hyoung Kyu Cho, Seung-Jun Lee, and Han Young Yoon(KAERI) Jae Jun Jeong(PNU) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Coherent Calculation for Air-water Flow and Boiling Flow by Using CUPID Code | Ik Kyu Park, Han Young Yoon, and Hyung Kyu Cho(KAERI) An Sook, Seol(KAIST) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Best Estimate Approach for the Simulation of Void Reactivity of CANDU Type Reactor Using the MARS Code | Kap Kim(KINS) Byoung Sub Han(ENESYS) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | ATLAS Steam Generator Tube Rupture Accident Simulation Using SPACE Code | Chang-Keun Yang, Sang-Jun Ha, and Hwang-Yong Jun(KHNP) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Optimization of Heat Transfer Mode Determination in TASS/SMR-S Core Heat Transfer Model | Soo Hyoung Kim, Seong Wook Lee, and Young-Jong Chung(KAERI) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Performance Evaluation for the Diameter and Material of Condensation Heat Exchanger Using the TASS/SMR-S Code | In Sub Jun, Soo Hyoung Yang, Kyoo Hwan Bae, and Young Jong Chung(KAERI) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Computation of Pressure Drop in Cross-flow through an In-line Tube Bundle | Youngmin Bae, Yu Mi Jeon, Yeong-Gil Kim, Seung Heon Yang, Han-Ok Kang, Young-In Kim, Cheon-Tae Park, | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | The Effect of Core Residual Heat on Success Criteria during the Shutdown and Low Power Operation | Moon-Oh Kim and Hee-Do Lee(ACT Co., Ltd.) Goon-Cherl Park(SNU) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary Simulation of PAFS Using the CUPID Code | Lee, Seung-Jun, Cho, Hyoung Kyu, and Yoon, Han Young(KAERI) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Natural Circulation Cooldown Analysis for APR 1400 Using the SPACE Code | Il Soon Park, Myung Taek Oh, Chan Eok Park, and Jong Joo Sohn(KEPCO E&C) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Study on Methodology for Establishment of the Minimum Allowable Fuel Channel Flow Rate in Steady State | In Young Kim, Yong Won Choi, and Un Chul Lee(SNU) Kap Kim(KINS) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | CFD Calculation of Turbulent and Thermal Mixing in a T-Junction: Comparison with Vattenfall Experimental Data | Dong-Gu Kang and Kwang-Won Seul(KINS) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Cross Flow Characteristics of the Core Simulator in SMART Reactor Flow Distribution Test Facility | J. Yoon, Y. I. Kim, Y. J. Chung, and W. J. Lee(KAERI) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Estimation of Porous Media Approach for Thermal Hydraulics of Nuclear Fuel Assembly | Byung Soo Shin, San Kyu Lee, Yong Bum Bae, Nam Seok Kim, and Oh Hyun Keum(KINS) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Study on the Secondary Thermal Power Reduction Factor of KSNP | Cha. Hyeng Ho(KHNP) Lee. Kyoong Jin(CSU) | PDF보기 | - |
Last Modified : 1998-Autumn
