학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2018-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.17(Thu) 13:00 | 로비 (3F) | Investigation of Nano-sized Oxide Particles in ODS Steels | Jinsung Jang, Man Wang, Chang Hee Han, and Tae Kyu Kim(KAERI), Xiaodong Mao(INEST), Heung Nam Han(SNU) | PDF보기 | - |
| 2018-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.17(Thu) 13:00 | 로비 (3F) | Hoop strength evaluation of triplex SiC composite tube using by oil compression pressures | Hyeon-Geun Lee, Daejong Kim, and Weon-Ju Kim(KAERI) | PDF보기 | - |
| 2018-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.17(Thu) 13:00 | 로비 (3F) | Effect of Electrochemical Property on Corrosion of CVD-SiC Ceramics in PWR Coolant Environments | Jung Ho Shin, Daejong Kim, Hyeon-Geun Lee, and Weon-Ju Kim(KAERI) | PDF보기 | - |
| 2018-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 09:00 | 201A (2F) | Measurement of Multi-Dimensional Distribution of Local Bubble Parameters in a Vertical Annulus under Subcooled Boiling Conditions | Yeon-Gun Lee and Ji-Woong Yoo(JNU), Sin Kim(CAU) | PDF보기 | - |
| 2018-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 09:20 | 201A (2F) | The Influence of Transverse Heat Flux Distribution on the Flow Instability for Subcooled Boiling Through a Narrow Rectangular Channel | Omar S. Al-Yahia, Taewoo Kim, and Daeseong Jo(KNU) | PDF보기 | - |
| 2018-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 09:40 | 201A (2F) | Study on Flow Field in the Core Inlet of PGSFR | Soon-Joon HONG, Ji-Seok KIM, and Jin-Seok HWANG(FNC Tech.), Dong-Jin EUH and Seok-Gyu CHANG(KAERI) | PDF보기 | - |
| 2018-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 10:00 | 201A (2F) | Benchmarking of the four-sensor optical fiber probe method for the measurement of local bubble parameters under the slug flow | Jeongmin Moon, Byongjo Yun, Jaejun Jeong, and Taeho Kim(PNU) | PDF보기 | - |
| 2018-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 10:20 | 201A (2F) | Two-Phase Air-Water Flow Regime and Transition Criteria For Vertical Upward And Vertical Downward Flow Direction In A Narrow Rectangular Channel | Vikrant Chalgeri and Ji Hwan Jeong(PNU), Tae Hyeon Kim(KHNP CRI) | PDF보기 | - |
| 2018-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 11:00 | 201A (2F) | Experimental Study of Dropwise Condensation Heat Transfer with Visualization of Droplet Distribution | Jae Young Choi and Yong Hoon Jeong(KAIST) | PDF보기 | - |
| 2018-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 11:20 | 201A (2F) | Experimental Study for Condensation Heat Transfer Enhancement by Using Robust Hydrophobic Coating | Junho Hong and Hyungdae Kim(KHU) | PDF보기 | - |
| 2018-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 11:40 | 201A (2F) | An Experimental Investigation on the External Condensation for a Vertical Tube under Forced Convection | Jiwoong Yoo, Un-Ki Kim, Yeong-Jun Jang, and Yeon-Gun Lee(JNU) | PDF보기 | - |
| 2018-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 09:00 | 203 (2F) | MARS-KS code Modification for Re-evaluation of Post-LOCA Long Term Cooling Behavior with in-vessel Downstream Effect of Debris in APR1400 | Andong SHIN, Yong Seok Bang, and Min Ki CHO(KINS) | PDF보기 | - |
| 2018-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 09:20 | 203 (2F) | Impact of k-factor at the Entrance from Downcomer to Broken Cold Leg on ECC Bypass | Young Seok Bang, Dong H. Yoon, Deog Y. Oh, and Il S. Lee(KINS) | PDF보기 | - |
| 2018-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 09:40 | 203 (2F) | Evaluation for Application of TRACE Code to LBLOCA Analysis of APR1400 Using Best Estimate Plus Uncertainties | Byung Gil Huh, Deog-Yeon Oh, Young Seok Bang, and Chae-Yong Yang(KINS) | PDF보기 | - |
| 2018-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 10:00 | 203 (2F) | Report on Participation in IAEA CRP: Application of Computational Fluid Dynamics (CFD) Codes for Nuclear Power Plant Design | Yun-Je Cho, Jae-Ryong Lee, and Han-Young Yoon(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
