移动式放射性废水应急处理装置的设计与试验研究  

Design and experimental study of mobile emergency treatment device for radioactive wastewater

作　　者：杨洋 陶建国 马若霞 毛霖 伍灵 周怡人 YANG Yang;TAO Jianguo;MA Ruoxia;MAO Lin;WU Ling;ZHOU Yiren(Technology Branch of Chongqing Yuanda Flue Gas Treatment Franchise Co.,Ltd.,Chongqing 401122,China;State Power Investment Group Co.,Ltd.,Beijing 100029,China)

机构地区：[1]重庆远达烟气治理特许经营有限公司科技分公司,重庆401122 [2]国家电力投资集团有限公司,北京100029

出　　处：《工业水处理》2023年第6期81-85,共5页Industrial Water Treatment

基　　金：国家重点研发计划项目(2016YFC1402506)。

摘　　要：为了应对核电站突发严重事故时产生的高含盐放射性废水,设计制造了一套处理量为5 m~3/h的移动式放射性废水应急处理装置。该装置采用了“过滤+反渗透+离子交换”的组合工艺。配制Co^(2+)、Sr^(2+)、Cs^(+)质量浓度均为100 mg/L,TDS=7 000 mg/L的模拟放射性废水,用于评价该处理装置的性能。结果表明,该移动式放射性废水应急处理装置对Co^(2+)、Sr^(2+)、Cs^(+)的总去污因子(DF)分别为1.19×10^(5)、1.02×10^(5)、7.30×10^(3),对3种核素的综合去污因子为1.74×10^(4),3种核素的总去除率大于99.99%;同时,该装置对模拟放射性废水中的盐类也具有良好的去除效果。基于该移动式放射性废水应急处理装置对废水中核素的优异去除效果,其可以作为核电站放射性废水的应急处理方案。A mobile radioactive wastewater emergency treatment device with a treatment capacity of 5 m3/h was de-signed and manufactured to cope with the high saline radioactive wastewater from the sudden serious accident of the nuclear power plant.The device adopted a combination process of filtration,reverse osmosis and ion exchange.Simulated radioactive wastewater with mass concentrations of 100 mg/L Co^(2+),Sr^(2+)and Cs^(+)and TDS=7000 mg/L was prepared and used to evaluate the performance of the device.The results showed that the total decontamination fac-tor(DF)of the device for Co^(2+),Sr^(2+)and Cs^(+)were 1.19×10^(5),1.02×10^(5) and 7.30×10^(3),respectively.The combined de-contamination factor of the device for the three nuclides was 1.74×10^(4),with a removal rate greater than 99.99%.At the same time,the device also had a good effect on the removal of salt in the simulated radioactive wastewater.Based on the efficient removal of nuclides from wastewater,this device could be used as an emergency treatment scheme for radioactive wastewater in nuclear power plants.

关 键 词：放射性废水 移动式装置 核电站事故 应急处理 

分 类 号：X77[环境科学与工程—环境工程]