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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
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 -
Last Modified : 1998-Autumn