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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) 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 -
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 -
Last Modified : 1998-Autumn