核电厂废液处理系统净化塔分离模型及试验研究

Separation Model and Experimental Research on Purification Column in Liquid Waste Treatment System of Nuclear Power Plants

分析净化塔试验装置对不易挥发性放射物质的分离水平,并在专门设计的净化塔试验装置上进行试验。结果显示:净化塔试验结果与理论分析计算结果一致,确认了理论分析所采用的计算方法和模型的合理性。运用该理论计算模型对核电厂废液处理系统(TEU)中的蒸发装置进行分析。分析结果表明:核电厂采用3块筛板及丝网除沫器的设置合理,可以实现核电厂的运行要求且安全裕度较高。

Separation level of non-volatile radioactive substances was analyzed by theoretical method, and specially designed purification tower was tested. The results showed that the experimental result was unanimous of which was gained by theoretical method. So the theoretical method and calculation model were rational. The theoretical model was applied on the evaporation equipment in the liquid waste treatment TEU system of a nuclear power plant, and the results showed that 3 sieve plates with wire mesh demister was rational and it could satisfy the requirement of nuclear power plant with a high safety margin.