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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Development of Parametric Correlation and Source Term Evaluation Sung Il Kim(KAERI) and Kwang Soon Ha(KAERI) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) An Apparatus and Method for a Hemispherical Thickness Measurement using Magnetostrictive Ultrasonic Wave Kil-Mo Koo and Hwan-Yeol Kim(KAERI), Chiseung Park(UMI) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Effect of SIT-FD Modeling on Severe Accident Analysis Using MAPP5 Dong-Kyu Lee(KNFC), Hyungsok Lee(KNFC), Chang-Suk Cho(KNFC), and Geol-Woo Lee(KNFC) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Experimental research on aerosol decontamination performance of the filtered containment venting system in ARIEL test facility Jae Bong Lee(KAERI), Sung il Kim(KAERI), Jaehoon Jung(KAERI), Kwang Soon Ha(KAERI), and Hwan Yeol Kim(KAERI) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) The Preliminary Analysis for SBO accident in SMART with PCCS system Jong Hwa Park(KAERI), Sang Ho Kim(KAERI), and Rae Joon Park(KAERI) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Preliminary Calculation?for Passive Autocatalytic Recombiner Model of Severe Accident Containment Analysis Package Code Jaehwan Park(KHNP CRI), Yu Jung Choi(KHNP CRI), and Tae Hyub Hong(KHNP CRI) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Experimental Study on Pool Boiling Heat Transfer in Water Using Sintered Copper Microporous Coatings on Metal Surface Hwan Yeol Kim(KAERI), Seungchul Jun(UTD), and Seung M. You(UTD) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Effect of Air-Curtain Discharge Speed on the Effectiveness of Vortex-like Air-Curtain Approach for Severe Accident Management Sana Ullah(KAIST) and Man Sung Yim(KAIST) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Methodology of HPME/DCH analysis in CINEMA code JaeGwon Lee((KNHP CRI).) and ChangHwan Park((KNHP CRI).) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Evaluation of a spray technology to capture aerosols for severe accident mitigation?outside a nuclear power plant JongWook Go(KAIST) and ManSung Yim(KAIST) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) A Study of Nuclear Reactor Pressure Vessel Lower Head Penetration using Numerical Analysis Wung Jae Wang(KAIST), Jaehoon Jung(KAERI), Hwan Yeol Kim(KAERI), and Man Sung Yim(KAIST) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Current Status of Study for Severe Accidents in the SFPs of CANDU Plants Sung-deok Yi(NESS), Yong-mann Song(KAERI), Bo-wook Rhee(KAERI), Eun-kyung Jang(NESS), and Seoung-rae Kim(NESS) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Assessment of Mitigating Strategies using CFVS and CVWM at CANDU plant under Severe Accident Conditions gaeul choi((KNHP CRI).), keohyoung lee((KNHP CRI).), and jinyong lee((KNHP CRI).) PDF보기 PPT보기
2017-Spring 5P : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) A methodology for Level 1 PSA Success Criteria during Mid-loop operation for Low Power Shutdown Probabilistic Safety Assessment Jaegab Kim(KEPCO E&C) and Tae Hee Hwang(KEPCO E&C) PDF보기 -
2017-Spring 5P : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) ISLOCA Analysis for a Typical 1000MW PWR: Accident Progression, FP Distribution, and Accident Management Sooyong Park(KAERI), Kwang-Il Ahn(KAERI), and Dong-San Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn