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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2022-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.19(Thu) 13:00 로비 (3F) Characterization of 3D Printed Functionally Graded Material for Nuclear Reactor Ji-Hyun Yoon, Wanchuck Woo, and Giseung Shin(KAERI) PDF보기 -
2022-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.19(Thu) 13:00 로비 (3F) Improvement of Corrosion Resistance of Stainless Steel Used in Cooling Water Component by Plasma Electrolysis Jun Heo, Jaewoo Lee, and Sung Oh Cho(KAIST) PDF보기 -
2022-Spring 4E : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.19(Thu) 13:00 로비 (3F) Effect of Process Conditions on the Characteristics of Sol Gel TiO2 Dip Coating Wan Young Maeng, Ji Hae Yoon, Dong Jin Kim, and Young Bum Chun(KAERI) PDF보기 -
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 09:00 400호 (4F) Forced Convection Heat Transfer of the Heating Packed Bed Varying the Sphere Diameter and Bed Height Je-Young Moon(KAERI), Bum-Jin Chung(KHU) PDF보기 -
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 09:20 400호 (4F) Flow Characteristics of Foamed Surfactant Solution in the Vertical Pipe for Decommissioning Nuclear Power Plant Hyoin Lee, Eunsik Sung, and Ji Hwan Jeong(PNU) PDF보기 -
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 09:40 400호 (4F) Experimental Investigation of CHF on Helical Finned Heater under the Static Inclination and Rolling Conditions Chang Won Lee, Jin -Seong Yoo, Hee Pyo Hong, Goon-Cherl Park, and Hyoung Kyu Cho(SNU), Geon Woo Kim(KINS) PDF보기 -
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 10:00 400호 (4F) Resemblance of Critical Current Density to Critical Heat Flux Hae-Kyun Park and Bum-Jin Chung(KHU) PDF보기 -
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 10:20 400호 (4F) Heat Transfer Performances of Printed Circuit Heat Exchangers with Airfoil and Straight Channels for Helium Brayton Cycle Recuperator Designs Sungkun Chung, Seong Min Shin, Namhyeong Kim, Su Won Lee, Moo Hwan Kim, and HangJin Jo(POSTECH) PDF보기 -
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 11:00 400호 (4F) Influence of Bed Diameter (D) on the Natural Convection of a Packed Bed Sang Soo Yoon, Hyun Ha Ahn, and Bum Jin Chung(KHU) PDF보기 -
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 11:20 400호 (4F) Experimental Thermal Evaluation of Sodium Heat Pipe with Different Inclination Angle Dong Hun Lee and In Cheol Bang(UNIST) PDF보기 -
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 11:40 400호 (4F) Modified Hydrodynamic Instability Model in Consideration of Heater Configuration during Pool Boiling SeockYong Lee, Sehyeon Park, and HangJin Jo(POSTECH) PDF보기 PPT보기
2022-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 12:00 400호 (4F) Feasibility Study of Hybrid Heat Pipe Control Rod Application on Nuclear Power Plant using UNIST Reactor Innovation LOop(URI-LO) Hyeon Ji Kim, Do Yeong Lim, and In Cheol Bang(UNIST) PDF보기 -
2022-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 09:00 401호 (4F) Numerical Comparison of Hydraulic Characteristics in KAERI 61-PIN Wire-Wrapped Fuel Assembly using STAR-CCM+ and ANSYS CFX Gi Uk Choi and Jae Ho Jeong(Gachon Univ.), Jonggan Hong and Yo Han Jung(KAERI) PDF보기 -
2022-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 09:20 401호 (4F) Investigation of the Heat Removal Capability of the Hybrid Control Rod in Natural Circulation-type SMR under Station Black Out Accident with MARS-KS code Ji Yong Kim, Ye Yeong Park, and In Cheol Bang(UNIST) PDF보기 -
2022-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 09:40 401호 (4F) Developing Correlation of Bubble Departure Diameter in Upward Subcooled Flow Boiling Based on Force Balance Model Long Doan Manh, Jeongmin Moon, Jinyeong Bak, Jae Jun Jeong, and Byong-Jo Yun(PNU) PDF보기 -
Last Modified : 1998-Autumn