학술발표회 논문집
Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
---|---|---|---|---|---|---|---|
2018-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 10:20 | 203 (2F) | Development and Validation of CUPID Reactor Vessel Module | Ik Kyu Park, Han Young Yoon, Seung Jun Lee , Yun Je Cho, and Jae Ryong Lee(KAERI) | PDF보기 | - |
2018-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 11:00 | 203 (2F) | The Implementation of Mixing Vane Directed Cross Flow Model in CUPID for Subchannel Scale T/H Analysis | Seul-Been Kim, Jae-Ho Lee, Goon-Cherl Park, and Hyoung-Kyu Cho(SNU) | PDF보기 | PPT보기 |
2018-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 11:20 | 203 (2F) | On the Form of Momentum Convection Term in the SPACE Multi-Dimensional Thermal-Hydraulic Module | Dongha Lee, Byongjo Yun, and Jae Jun Jeong(PNU), Seungwook Lee(KAERI) | PDF보기 | - |
2018-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.17(Thu) 11:40 | 203 (2F) | Using Machine Learning to Estimate Bubble Size in Turbulent Bubbly Flows | Jungwoo Kim(SEOULTECH), Seongwon Kang and Serin Yoon(Sogang Univ.), Dongjoo Kim(Kumoh Natl. Instl. Tech.) | PDF보기 | - |
2018-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 09:00 | 201A (2F) | Effect of inclination angle and pressure for the CHF under the IVR-ERVC condition | Jun Yeong Jung, Dong Hoon Kam, and Yong Hoon Jeong(KAIST), Hae Min Park(KAERI) | PDF보기 | - |
2018-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 09:20 | 201A (2F) | Flow boiling heat transfer on downward-facing coated large surface of inclined channel wall | Kiwon Song, Moo Hwan Kim, and Shripad T. Revankar(POSTECH), Seongchul Jun and Seung Moon You(UT Dallas), Hwan Yeol Kim(KAERI) | PDF보기 | - |
2018-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 09:40 | 201A (2F) | Critical heat flux enhancement of nuclear fuel cladding with a nano-porous oxide film by anodization | Hyoung Suk Yu and Yong Hoon Jeong(KAIST) | PDF보기 | - |
2018-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 10:00 | 201A (2F) | Pool boiling experiments for critical heat flux using Fe3O4, SiO2 nanoparticles on a flat-type upward surface | Min Suk Lee, Dong Hoon Kam, and Yong Hoon Jeong(KAIST) | PDF보기 | - |
2018-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 10:20 | 201A (2F) | An Experimental Study on Flow Boiling Critical Heat Flux on Axisymmetric Sudden Expansion Channel | Yong Jin Kim, Sub Lee Song, Soon Heung Chang, and Yong Hoon Jeong(KAIST), Sang-Ki Moon(KAERI) | PDF보기 | - |
2018-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 10:40 | 201A (2F) | A condensation model for the PAFS heat exchanger tube under the pure steam conditions | Taehwan Ahn, Jinhoon Kang, Jaejun Jeong, and Byongjo Yun(PNU) | PDF보기 | - |
2018-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 09:00 | 203 (2F) | Preliminary CFD Aanalysis on Operating a ontainment Spray System | Taehyub Hong, Yujung Choi, and Jong Wook Go(KHNP CRI) | PDF보기 | - |
2018-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 09:20 | 203 (2F) | Development of PIRTs for SPACE code extension to Application into Research Reactors | Hyeonil Kim, Byeonghee Lee, Su-Ki Park, Youn-Gyu Jung, Jong Pil Park, Donghyun Kim, Dong-Wook Jang,\nCheol Park, and Seung-Wook Lee(KAERI) | PDF보기 | - |
2018-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 09:40 | 203 (2F) | Film Boiling Heat Transfer on an Oscillating Surface | Young Seock An and Byoung Jae Kim(CNU) | PDF보기 | - |
2018-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 10:00 | 203 (2F) | Assessment Calculation of PKL H1.1 by using SPACE Code | Sung Won Bae and Kyung Doo Kim(KAERI) | PDF보기 | - |
2018-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Fri) 10:20 | 203 (2F) | Modification of the dynamic motion model in MARS for marine reactor thermal-hydraulic analysis | Hee-Kwan Beom, Geon-Woo Kim, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) | PDF보기 | - |
Last Modified : 1998-Autumn