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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2018-Autumn 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 13:00 컨벤션센터로비 (2F) Effects of Inlet Flow Mal-Distribution on the Thermal Margin Model of SMART-PPE Mazen Abdullah Baamer(K.A.CARE), Kyong-Won Seo(KAERI) PDF보기 -
2018-Autumn 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 13:00 컨벤션센터로비 (2F) CFD Analysis on Thermal-Hydraulic Behavior in Emergency Cooldown Tank of SMART Passive Residual Heat Removal System Kyung Jun Kang, Seong Dae Park, and Hyun Sik Park(KAERI) PDF보기 -
2018-Autumn 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 13:00 컨벤션센터로비 (2F) Computational Analysis for Pressure Loss Coefficient in a Sudden Contraction and Double Expansion Rashad Y. Abuaish(K.A.CARE), Youngmin Bae, Hyunjun Cho, Cheong B. Chang, and Young I. Kim(KAERI) PDF보기 PPT보기
2018-Autumn 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 13:00 컨벤션센터로비 (2F) Design Improvement in a Pump Intake in Prototype Gen-IV Sodium Cooled Fast Reactor using Computational Fluid Dynamics Seung Ho Ryu, Huee-Youl Ye and Ji-Woong Han(KAERI) PDF보기 -
2018-Autumn 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 13:00 컨벤션센터로비 (2F) Preliminary Evaluation of Interfacing System Loss of Coolant Accident for OPR1000 Jae Hwa Koh(KHNP CRI) PDF보기 -
2018-Autumn 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 13:00 컨벤션센터로비 (2F) Analysis of Heat Transfer Performance of a Fork-End Heat Pipe using MARS-KS Sangmin Park, Changhwan Lim, Jonghwi Choi, and Hyungdae Kim(KHU), Taewan Kim(INU) PDF보기 PPT보기
2018-Autumn 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 13:00 컨벤션센터로비 (2F) ATOM Secondary Side Pump Modeling for Developing Artificial Intelligence Operational Scheme Doh Hyeon Kim and Jeong Ik Lee(KAIST) PDF보기 -
2018-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.25(Thu) 09:00 그랜드홀 (1F) Markov Chain Monte Carlo for Reliability Analysis: A Concept Exploration Jeremiah Mbazor and Marco Torbol(UNIST) PDF보기 -
2018-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.25(Thu) 09:20 그랜드홀 (1F) A Case Study of Methodology for Common Cause Failure Modeling in Multi-Unit PSA Model Seunghyun Jang, Yein Seo, and Moosung Jae(HYU) PDF보기 -
2018-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.25(Thu) 09:40 그랜드홀 (1F) A Case Study of Multi-Unit Probabilistic Safety Assessment Modeling for Two Units Dohyun Lim, Wonjong Song, Byeongmun Ahn, and Moosung Jae(HYU) PDF보기 -
2018-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.25(Thu) 10:00 그랜드홀 (1F) New Methodology on Combining Source Term Categories for Multi-Unit Level 3 PRA Wonjong Song, Seungwoo Kim, and Moosung Jae(HYU) PDF보기 -
2018-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.25(Thu) 10:40 그랜드홀 (1F) Application of Off-site Consequence Calculation Method for Multi-Unit Nuclear Power Plants Hye Rin Lee, Gee Man Lee, and Woo Sik Jung(Sejong Univ.), Seok-Jung Han(KAERI) PDF보기 -
2018-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.25(Thu) 11:00 그랜드홀 (1F) Modelling Approaches in KHNP Multi-Unit PSA Project Kyemin Oh, Hojun Jeon, and Jeong Seon Park(KHNP CRI) PDF보기 -
2018-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.25(Thu) 11:20 그랜드홀 (1F) Canadian Nuclear Industry Position on Proposals .vs. Actual Measures Undertaken to Reduce Severe Accident Risk from PHWRs Sunil Nijhawan(PROLET) PDF보기 -
2018-Autumn 6B : 원자력 안전 (Nuclear Safety) 10.25(Thu) 09:00 소회의실3 (2F) MCR Safety Dose Assessment in LOCA Condition of Westinghouse Type NPP Seung Chan LEE, Min Jeong Kim, Sun Min Kim, and Duk Joo Yoon(KHNP CRI) PDF보기 -
Last Modified : 1998-Autumn