二重管流路の液滴付着率評価(原子炉伝熱流動解析の革新(2),原子炉伝熱流動解析の革新)

概要

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To predict thermal-hydraulic performance of BWR fuel bundle, such as the critical power, the subchannel analysis is usually performed. In the subchannel analysis code, many empirical correlations are included. The one of the important correlations is that for the rate of droplet deposition. However, most available correlations for deposition rate were deduced from experimental data for simple cross-sectional geometry such as round tube and rectangular duct. Thus, the cross-sectional geometry effect on the droplet deposition rate was studied numerically using the Eulerian-Lagrangian analysis method. As the first step, the droplet deposition rate onto the inner and outer walls in annulus channel were estimated. It was shown numerically that the droplet deposition rate onto the outer surface is larger than that onto the inner surface.
2004-09-04