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냉각수 유동을 고려한 핵 연료봉의 유체-고체 연계 해석
김해란(Hai-Lan Jin),이영신(Young-Shin Lee),이현승(Hyun-Seung Lee),김영지(Young-Ji Kim),박남규(Num-Kyu Park),전경락(Kyung-Rok Jeon) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.3
This study has been conducted to investigate the flow characteristics and nuclear reactor fuel rod stress under effect of coolant. Fluid structure interaction(FSI) analysis on nuclear reactor fuel rod was performed. Both fluid analysis of the coolant which flow in the axial direction and a structural analysis using the pressure data resulting from fluid analysis were carried out under different output flow velocity conditions. In the flow analysis, streamlines and maximum flow velocity at different domain were easily acquired from the analysis results. In the structure analysis, maximum stress of the nuclear reactor fuel rod was calculated and the location that has the maximum stress was found.