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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2022-Autumn 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 13:00 컨벤션홀I (3F) Study on the Velocity Distribution of Turbulent Steam Jet from the Non-Circular Nozzle Exit Jaewon Myeong, Hyeon Gyeom Kim, and Weon Gyu Shin(CNU) PDF보기 -
2022-Autumn 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 13:00 컨벤션홀I (3F) Local Reverse Heat Transfer of Condensation Heat Exchanger with Non-condensable Gas Jin-Hwa Yang, Tae-Hwan Ahn, Hwang Bae, and Hyun-Sik Park(KAERI) PDF보기 -
2022-Autumn 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 13:00 컨벤션홀I (3F) Applying Supervised Learning Algorithm to Nuclear Power Plant Severe Accident Data Generated from MAAP Code Seok Ho Song and Jeong Ik Lee(KAIST) PDF보기 -
2022-Autumn 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 13:00 컨벤션홀I (3F) Evaluation of the Effect of Fuel Relocation on the current LBLOCA Safety Analysis using SPACE Hyungsuk Lee, Tae Beom Lee, and Sang Ik Lee(KEPCO NF) PDF보기 -
2022-Autumn 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 13:00 컨벤션홀I (3F) Feasibility Study of Wall Temperature Measurement Method using Temperature-Sensitive Fluorescent Material for Application to High-Pressure Flow Boiling Experiment Woojien Lee, Jonghwi Choi, Ahyeong Cho, and Hyungdae Kim(KHU) PDF보기 -
2022-Autumn 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 10.20(Thu) 13:00 컨벤션홀I (3F) Primary PFHE Design for Chloride Based Molten Salt Fast Reactor Sunghyun Yoo, In Woo Son, Sungwook Choi, and JeongIk Lee(KAIST) PDF보기 PPT보기
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 09:00 600B호 (6F) Benchmarking of PHEBUS FPT0 Experiment by using CINEMA and MELCOR Code Chang Hyun Song, Joon Young Bae, Wonjun Choi, and Sung Joong Kim(HYU), Donggun Son and Jun-Ho Bae(KAERI) PDF보기 -
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 09:20 600B호 (6F) A Benchmarking Study for CINEMA and MELCOR Codes Subject to Core Degradation Phase of PHÉBUS FPT 1 by using Dynamic Time Warping Joon Young Bae, Chang Hyun Song, Wonjun Choi, and Sung Joong Kim(HYU), Donggun Son and Jun-Ho Bae(KAERI) PDF보기 -
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 09:40 600B호 (6F) High Temperature Fuel Rod Bundle Analysis of QUENCH-06 Experiment Using CINEMA Woonho Jeong and Yong Hoon Jeong(KAIST), Dong Gun Son(KAERI) PDF보기 -
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 10:00 600B호 (6F) A Preliminary Validation and Sensitivity Analysis of FARO L-14 Experiment using Steam Explosion Module of CINEMA Seokwon Whang and Hyun Sun Park(SNU), Soon-ho Park(FNC Tech.) PDF보기 PPT보기
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 10:20 600B호 (6F) Validation of OECD CCI-2 Experiment using MCCI Module of CINEMA Jun Sung Choi and Eung Soo Kim(SNU), Soon Ho Park(FNC Tech.) PDF보기 -
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 11:00 600B호 (6F) Application of CINEMA Code to CCI-5 Analysis Eungsoo Kim and Taehwan Kim(SNU), Soonho Park(FNC Tech.) PDF보기 -
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 11:20 600B호 (6F) A Study on Internal PSA for a KAERI Molten Salt Reactor Kilyoo Kim and SangJi Kim(KAERI) PDF보기 -
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 11:40 600B호 (6F) Case Study for Event Scenario Uncertainty Analysis Using DICE Yuntae Gwak, Sejin Baek, Dohun Kwon, and Gyunyoung Heo(KHU) PDF보기 PPT보기
2022-Autumn 6A : 원자력 안전 (Nuclear Safety) 10.20(Thu) 12:00 600B호 (6F) Uncertainty Analysis for Frequency of Heat Pipe Cascading Failure Event in Micro Modular Reactor Gyun Seob Song and Man Cheol Kim(CAU) PDF보기 -
Last Modified : 1998-Autumn