학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2023-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.18(Thu) 13:00 | Lobby (3F) | Development of Wear Prediction Model for Steam Generator Tubes | Daeyeop Kwon and Chi Bum Bahn(PNU), Heejae Shin and Young-Jin Oh(KEPCO E&C) | PDF보기 | - |
| 2023-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:30 | 302 (3F) | Evaluation Performance of Spent Fuel Pool Cooling System with Water Jacket Heat Pipe | Sanghoon Lee, Min Suk Lee, Wooseong Park, and Young Hoon Jeong(KAIST) | PDF보기 | - |
| 2023-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:50 | 302 (3F) | Design and Evaluation of a Hybrid Cesium Heat Pipe Shutdown Rod as a Passive Safety System for Microreactors | Dong Hun Lee and In Cheol Bang(UNIST) | PDF보기 | - |
| 2023-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 14:10 | 302 (3F) | Preliminary Study on Effective Thermal Mass of Supercritical Carbon Dioxide Heat Exchanger | In Woo Son, Gi Hyeon Kim, Seung Kyu Lee, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2023-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 14:30 | 302 (3F) | Simultaneous Two-Axis Force and Displace Measurement Techniques for Vortex Shedding in SMART100 Heat Exchanger Tube Array | Chan Lee, Dongseok Oh, Kanghee Lee, Suho Kim, and Heungseok Kang(KAERI) | PDF보기 | - |
| 2023-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 14:50 | 302 (3F) | Bended Zone Tube Assembly Vibration of Coiled Steam Generator Under Downward Flow | Kang-Hee Lee, Heung-Soek Kang, Sung-Wuk Lee, and Tae-Hyun Chun(KAERI) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 09:00 | 301 (3F) | Analysis of SBLOCA for CRDM Nozzle Rupture with Loss of Safety Injection at the ATLAS Experimental Facility using the MARS-KS 1.5 and TRACE V5.0 Patch 6 | Hyunjoon Jeong and Taewan Kim(INU) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 09:20 | 301 (3F) | Experimental Study on the Main Steam Line Break (MSLB) Accidnet Accompanied by the Loss of Shutdown Cooling System(SCS) based on the Risk/Performance Information | Yusun Park, Byoung Uhn Bae, Jong Rok Kim, Jae Bong Lee, Seok Cho, Nam Hyun Choi, and Kyoung Ho Kang(KAERI), Jae Beol Hong and Hyun Bin Chang(FNC Tech.) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 09:40 | 301 (3F) | Experimental Investigation of Thermal-hydraulic Behavior and Safety Performance of Reactor Coolant System and Containment During a Steam Line Break Using ATLAS-CUBE Facility | Jae Bong Lee, Jongrok Kim, Yusun Park, Kyoung-Ho Kang, and Byoung-Uhn Bae(KAERI) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 10:00 | 301 (3F) | Evaluation of SPACE Predictive Capability for Horizontal In-Tube Condensation under Low Pressure and Low Mass Flux Conditions | Sang Gyun Nam, Seong-Su Jeon, and Soon-Joon Hong(FNC Tech.) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 10:40 | 301 (3F) | Analysis of Thermal Mixing Behavior of the Emergency Cooling Tank using the CUPID Code | Yun-Je Cho, Seong Jun Lee, and Han Young Yoon(KAERI) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 11:00 | 301 (3F) | Analytical Investigation on Natural Circulation and Flow Instability in the FINCLS Facility for SMART | Hyun-Sik Park, Byong-Guk Jeon, Jin-Hwa Yang, Sunil Lee, Hyun-Gi Yoon, Sung-Uk Ryu, Sung-Jae Yi, Yoon-Gon Bang, and Hwang Bae(KAERI) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 11:20 | 301 (3F) | Secondary System Modeling Guideline in Use of MARS-KS Code for Nuclear Renewable Hybrid Energy Systems | Young Seok Bang, Jungjin Bang, Seong-Su Jeon, Bub Dong Chung, and Youngsuk Bang(FNC Tech.) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 11:40 | 301 (3F) | The Effect of Presence of Irradiation Rig on Research Reactor Core Flow Distribution | Taeil Kim, Yohan Lee, Donkoan Hwang, WooHyun Jung, Nakjun Choi, and HangJin Jo(POSTECH), Jonghark Park, Kiwon Song, and Hyung Min Son(KAERI) | PDF보기 | - |
| 2023-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Fri) 12:00 | 301 (3F) | Modeling of Swing Check Valve in Support of Prediction of Passive Safety Systems Performance | Young Seok Bang, Ju Yeop Park, and Yong Seog Choi(KINS) | PDF보기 | - |
Last Modified : 1998-Autumn
