【摘要】 叙述了低压低流速下过冷沸腾汽泡脱离点的试验研究。试验是为确定自然循环池式核供热堆的热工水力学参数而进行的。试验本体采用了透明的垂直环形通道,电加热元件的尺寸及形状与核燃料元件相同。过冷沸腾汽泡脱离点是用目视方法确定的。更多还原

【Abstract】 An experimental study to investigate bubble detachment point in the subcooled boiling at low pressure and velocity is introduced. The purpose of this experiment was to determine the thermohydraulic parameters in pool ype nuclear heating reactor with natural circulation. The test section was composed of transparent vertical annulus-es. The shape and size of electric heating rods were similar to nuclear fuel rods. The bobble detachment point of subcooled boiling was identified by visual method.更多还原