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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2022-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 10:00 401호 (4F) SPACE Validation on a Steam Generator Tube Rapture Experiment with SMART-ITL Facility Eslam Bali and Sulatn Al-Faifi(KACARE), Kyung Doo Kim(KAERI) PDF보기 PPT보기
2022-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 10:20 401호 (4F) Analysis of SBLOCA for CRDM Nozzle Rupture with LSI at the ATLAS Experimental Facility using the MARS-KS 1.5 Hyunjoon Jeong and Taewan Kim(INU) PDF보기 -
2022-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 11:00 401호 (4F) Thermal Hydraulic Behavior Analysis of VANAM-M3(ISP-37) Experiment using SACAP Code Yo Han Kim, Woonho Jeong, and Yong Hoon Jeong(KAIST), Soon Ho Park(FNC Tech.) PDF보기 -
2022-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 11:20 401호 (4F) Improvement of Crossflow Model of MARS-KS by Introducing Inter-channel Turbulent Mixing Model Yunseok Lee and Taewan Kim(INU) PDF보기 -
Last Modified : 1998-Autumn