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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Computational Study for the Diameter Effect on Condensation Heat Transfer on Outer Surface of a Heat Exchanger Tube Chang-Won Lee, Hyoung-Kyu Cho, and Goon-Cherl Park(SNU) PDF보기 -
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Coupled Calculation of SPACE and FRAPTRAN Seung Wook LEE, Hyo Chan KIM, and Kyung Doo KIM(KAERI) PDF보기 -
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Design optimization of a heat exchanger in PCCS using LMTD method Yeo-Ul Song(KHNP CRI) PDF보기 -
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Implementation of the subchannel flow mixing model into the SPACE v3.0 code Dongwi Kim, Jaejun Jeong, and Byongjo Yun(PNU) PDF보기 -
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Assessment of Wall Condensation Models Using CUPID Code Jihyun Sohn(UST), Han Young Yoon(KAERI) PDF보기 -
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Enhancement of Fluid-to-Fluid Scaling Criteria for Modeling Condensation in Horizontal Tubes Under Stratified Flow Conditions Khalid Khasawneh and Yong Hoon Jeong(KAIST) PDF보기 -
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Comparison between CUPID and CTF for Subchannel Scale Thermal-Hydraulic Analysis of Single Fuel Assembly Problem Jae-Ho Lee, Seul-Been Kim, Goon-Cherl Park, and Hyoung-Kyu Cho(SNU) PDF보기 PPT보기
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Investigation of ECC Delivery in UPTF Test Using CUPID-RV Code Seung Jun Lee, Yun Je Cho, Ik Kyu Park, Han Young Yoon, and Jae Ryong Lee(KAERI) PDF보기 -
2018-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.17(Thu) 13:00 로비 (3F) Analysis of Boiling Instability in Natural Circulation Conditions in Multiple Tube using the TRACE Code Hyun Jae Kim Jung Jin Bang, and Dong-Wook Jerng(CAU) PDF보기 -
2018-Spring 6A : 원자력 안전 (Nuclear Safety) 5.17(Thu) 09:00 삼다홀A (3F) A Study of the Failure Criterion for the Steel Pipe Components Under Seismic Loading Condition Sung-Jin Chang, Sung-Wan Kim, and Bub-Gyu Jeon(PNU), Dae-Gi Hahm(KAERI) PDF보기 -
2018-Spring 6A : 원자력 안전 (Nuclear Safety) 5.17(Thu) 09:20 삼다홀A (3F) Rocking Stiffness of Electric Cabinet Considering the Local Deformation at the Base Minsoo Han and Sung-Gook Cho(INNOSE TECH), Kee-Jeung Hong(KMU), Abhinav Gupta(NCSU) PDF보기 -
2018-Spring 6A : 원자력 안전 (Nuclear Safety) 5.17(Thu) 09:40 삼다홀A (3F) A Brief Comparative Study on Stress Tests Specifications of the EU and Korea Cheol-Seung Cheon and Sung-Tae Yang(KHNP) PDF보기 -
2018-Spring 6A : 원자력 안전 (Nuclear Safety) 5.17(Thu) 10:00 삼다홀A (3F) Preliminary Study on the Cooling Performance of Passive Emergency Core Cooling System Sung Uk Ryu, Sun-Il Lee, Yu-Na Kim, Seok Cho, Kyoung-Ho Kang, and Sung-Jae Yi(KAERI) PDF보기 -
2018-Spring 6A : 원자력 안전 (Nuclear Safety) 5.17(Thu) 10:20 삼다홀A (3F) Considerations of HRA for Domestic Fire PSA Sun Yeong Choi and Dae Il Kang(KAERI) PDF보기 -
2018-Spring 6A : 원자력 안전 (Nuclear Safety) 5.17(Thu) 11:00 삼다홀A (3F) A Study on the Fire Retardant Performance Depending on Accelerated Degradation of Non-Class 1E Cable Jueun Lee and Jihyun Kwark(FILK), Young Seob Moon and Sang Kyu Lee(KINS) PDF보기 -
Last Modified : 1998-Autumn