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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2018-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Fri) 11:00 203 (2F) Simulation of Station Black Out accident scenario (PKL H2.2) in PKL test facility Jong Hyuk Lee, Kyung Doo Kim, and Seung Wook Lee(KAERI) PDF보기 -
2018-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Fri) 11:20 203 (2F) A Preliminary CHF Model Development and Data Comparison with Vertical Heaters under Pool Boiling Conditions Dong Hoon Kam and Yong Hoon Jeong(KAIST) PDF보기 -
2018-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Fri) 13:30 201A (2F) Efficiency Assessment of Air-Cooling System as a Final Heat Sink of the ATOM System Doyoung Shin, Min Wook Na, Gwang Hyeok Seo, and Sung Joong Kim(HYU), Yonghee Kim and Jeong Ik Lee(KAIST) PDF보기 -
Last Modified : 1998-Autumn