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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2021-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 09:00 On-line Hydraulic Characteristic of Two-Phase Natural Circulation Loop as PCCS and Visualization Sun Taek Lim, Koung Moon Kim, and Ho Seon Ahn(INU), Dong-Wook Jerng(CAU) PDF보기 -
2021-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 09:20 On-line Natural Convection Phenomena of the Air in the Vertical Parallel Plates under High Wall Temperature Conditions Koung Moon Kim, Sun Taek Lim, and Ho Seon Ahn(INU), Dong-Wook Jerng(CAU) PDF보기 -
2021-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 09:40 On-line Test Result on a Small Break Loss-of-Coolant Accident Simulation for the Control Rod Driving Mechanism Nozzle Rupture with a Failure of Safety Injection Pump using the ATLAS Facility Jae bong Lee, Byoung-Uhn Bae, Yusun Park, Jongrok Kim, Seok Cho, Nam Hyun Choi, and Kyoung-Ho Kang(KAERI) PDF보기 -
2021-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 10:00 On-line Experimental Study on the Intermediate Break Loss of Coolant Accident (IBLOCA) with Total failure of Safety Injection Pumps Yusun Park, Byoung Uhn Bae, Jongrok Kim, Jae Bong Lee, Seok Cho, Nam Hyun Choi, and Kyoung Ho Kang(KAERI) PDF보기 -
2021-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 10:20 On-line Influence of the Mass flux, Inclination and Void Fraction on the Flow Boiling CHF using a Hydrogen Evolution System Jeong-Won Han, Hae-Kyun Park, and Bum-Jin Chung(KHU) PDF보기 -
2021-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 10:40 On-line Natural Convection Heat Transfer of Two Heating Spheres with Pitch-to-diameter Ratio Seong-Il Baek, Je-Young Moon, Dong-ho Shin, and Bum-Jin Chung(KHU) PDF보기 PPT보기
2021-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 11:00 On-line Heat Transfer Surface Morphology and Oxidation Effect on the CHF under Vertical Flow Boiling Considering the RPV Manufacturing and Operating Condition Jun Yeong Jung, Min Suk Lee, and Yong Hoon Jeong(KAIST) PDF보기 -
2021-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 11:20 On-line Commissioning Test of NEOUL-R Facility Designed for Critical Heat Flux Measurement under Rolling Motion Geon-Woo Kim, Jin-Seong Yoo, Heepyo Hong, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) PDF보기 -
2021-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.13(Thu) 09:00 On-line Analysis of Reactor Pressure Vessel Upper Head SBLOCA+LSI at the ATLAS Experimental Facility using the MARS-KS 1.5 Hyunjoon Jeong and Taewan Kim(INU) PDF보기 -
2021-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.13(Thu) 09:20 On-line Preliminary Analysis of SBLOCA for Innovative Small Modular Reactor (iSMR) using MARS-KS Code Sang Gyu Lim, Gil Bum Kang, Seon Heo, Sang Won Lee, Do Hwan Lee, and Yong Hak Kim(KHNP) PDF보기 -
2021-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.13(Thu) 09:40 On-line DNBR Evaluation for SLB Analysis by Multi-Dimensional Safety Analysis Jae Ryong Lee, Yun Je Cho, and Han Young Yoon(KAERI) PDF보기 -
2021-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.13(Thu) 10:00 On-line Numerical Study on Fluid-Thermal-Structure Interaction for a Solid Wire under Film Boiling Van Toan Nguyen and ByoungJae Kim(CNU) PDF보기 PPT보기
2021-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 09:00 On-line An Analysis on DVI SBLOCA for BANDI-60 Jeong Ju Kim, Jong Tae Seo, Han Rim Choi, and Jae Young Hun(KEPCO E&C) PDF보기 PPT보기
2021-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 09:20 On-line Development of Program Equivalent to RADTRAD for DBA Safety Evaluation Seung-Chan LEE(KHNP) PDF보기 -
2021-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.14(Fri) 09:40 On-line Effects of Fuel Relocation on LOCA Safety Analysis in APR1400 Joosuk Lee, Kyung-Won Lee, Kyunglok Baek, and Youngseok Bang(KINS) PDF보기 -
Last Modified : 1998-Autumn