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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2022-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 11:40 401호 (4F) Deformation of Zircaloy-4 Tube with High Internal Pressure under Film Boiling of Water at Atmospheric Pressure Van Toan Nguyen and Byoung Jae Kim(CNU) PDF보기 -
2022-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 13:30 402호 (4F) (초청발표) On the Scalability of Validation Data for LWR Safety Evaluation Chul-Hwa Song(KAERI) PDF보기 -
2022-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 14:00 402호 (4F) Analysis of Core Cooldown Performance According to the High Burnup Fuel Deformation Modeling Youn-Shil Kim, Young Kyun Kwack, Ji Hwan Kim, and Nhan Hien Hoang(EN2T), Young Seok Bang and Il Suk Lee (KINS) PDF보기 -
2022-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Thu) 14:20 402호 (4F) Example Analysis of Performance Issues in Passive Safety System using System Code Jehee Lee, Seong-Su Jeon, and Su Hyun Hwang(FNC Tech.), Ju-Yeop Park(KINS) PDF보기 -
Last Modified : 1998-Autumn