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机构地区:[1]中科华核电技术研究院有限公司,广东深圳518124
出 处:《热能动力工程》2015年第6期941-945,978,共5页Journal of Engineering for Thermal Energy and Power
摘 要:通过对核电站的硼酸回收系统中蒸发塔的分离效率进行理论分析,设计蒸发分离试验平台,对模拟料液进行蒸发试验,结果表明:回流比对蒸发效率影响较大,操作压力对蒸发效率影响并不显著。蒸发塔的回流比为20%和30%优于回流比为10%的蒸馏分离效果;蒸发塔在蒸汽流速超过额定流速25.9%的条件下,蒸馏液含硼浓度仍然小于5 mg/kg。放射性替代试验显示蒸发塔对不易挥发放射性核素的去污因子达到1 150。试验塔在保持与在役设备具有相同气相流速和液相流速的条件下,蒸馏液含硼浓度水平达到核电站的运行要求。Through a theoretical analysis of the separation efficiency of a vaporization tower in a boric acid recovery system in a nuclear power station,a vaporization and separation test rig was designed for performing a vaporization test of the liquid simulated. It has been found that the return flow ratio has a relatively big influence on the vaporization efficiency and the operating pressure has no remarkable influence on the vaporization efficiency. The distillation and separation efficiency when the return flow ratio of the vaporization tower is 20% and 30% respectively is superior to that when the return flow ratio of the vaporization tower is 10%. Under the condition of the steam flow speed in the vaporization tower exceeding the rated flow speed by 25. 9%,the boron content of the distillate remains less than5 mg / kg. The radiation alternative test results show that the decontamination factor of the vaporization tower to the radionuclides difficult to be volatile attains 1 150. It has been found that under the condition of the gas phase flow speed and liquid phase flow speed in the test tower keeping identical to those in the in-service equipment items,the boron content of the distillate can meet the requirements for operation of nuclear power stations.
分 类 号:TL941.12[核科学技术—辐射防护及环境保护]
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