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하중감소효과를 고려한 원자력 주증기 배관의 균열 안정성 평가
고봉환,김영진,석창성,Koh, Bong-Hwan,Kim, Yeong-Jin,Seok, Chang-Seong 대한기계학회 1996 大韓機械學會論文集A Vol.20 No.6
The objective of this paper is to evaluate the crack stability of the nuclear main stresm pipes, considering the load reduction effect due to the presence of circumferential throuth-wall crack. Also, the optimization techniques are adoped tosimulate the crack effect on the elbow component of the piuping system. By using a general beam elemetn which contains a discontinuous cross-section, the piping analysis is accomplished to acquire the reduced load. Considering this reduced load, it is feasible for the LBB application in nuclear main stresm pipe. Also, by combining an optimization program and a genaral finite element analysis program, the appropriate dimensions of the simplified beam elemtn which represents the effect of crack in elbow could be successfully determined.
고봉환,박승호,신동신 대한설비공학회 1999 설비공학 논문집 Vol.11 No.5
The objective of present study is to analyze a hot steel-tube cooling system as a kind of concentric triple-passage heat exchanger, whose inner tube is moving with a constant speed. Velocities and temperatures of an antioxidant gas flowing between inner and outer tubes are calculated theoretically for both laminar and turbulent flow regimes and used to give Nusselt numbers and friction factors with respect to various radius ratios and velocity ratios. In addition, it is shown that heat transfer coefficients based on ratios of average heat fluxes from inner and outer tubes might result in great errors for the temperature distributions of the flows, since the local heat transfer coefficients are dependent on the local heat flux ratios.
盧泰完,高鳳煥 弘益大學校 科學技術硏究所 1997 科學技術硏究論文集 Vol.8 No.-
In some classes of radiative and neutron transport problems that include strongly diffusing media, it might be impractical to refine the mesh enough to enter the regime of thin mesh cells. This is because such media are too optically thick to realistically allow sufficient mesh refinement. Considering that the simplified even-parity neutron transport equation is an approximation to the Boltzmann and even-parity transport equation, it is advantageous if the method has the correct diffusion limit; in other words, it gives generally accurate results in diffusing regimes, even when mesh cells are not thin. Our asymptotic analyses have shown that the so-called thick diffusion limit is satisfied by the finite element even-parity and simplified even-parity transport equations.