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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。
The experimental research on the point of sub-cooling boiling bubble at low pressure and low flow velocity is described. The experiment was conducted to determine the thermal-hydraulic parameters of a natural circulation pool-type nuclear reactor. The test body uses a transparent vertical annular channel, the size and shape of the electric heating element is the same as that of the nuclear fuel element. Subcooled boiling bubble break-off point is determined visually.