Industrial Water Treatment ›› 2023, Vol. 43 ›› Issue (6): 81-85.

• RESEARCH AND EXPERIMENT • Previous Articles     Next Articles

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

Yang YANG1(), Jianguo TAO2, Ruoxia MA1, Lin MAO1, Ling WU1, Yiren ZHOU1   

  1. 1. Technology Branch of Chongqing Yuanda Flue Gas Treatment Franchise Co. ,Ltd. ,Chongqing 401122,China
    2. State Power Investment Group Co. ,Ltd. ,Beijing 100029,China
  • Received:2023-03-23 Online:2023-06-20 Published:2023-06-25

移动式放射性废水应急处理装置的设计与试验研究

杨洋1(), 陶建国2, 马若霞1, 毛霖1, 伍灵1, 周怡人1   

  1. 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
  • 作者简介:

    杨洋(1991— ),硕士研究生。E-mail:

  • 基金资助:
    国家重点研发计划项目(2016YFC1402506)

Abstract:

A mobile radioactive wastewater emergency treatment device with a treatment capacity of 5 m3/h was designed 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 Co2+,Sr2+ and Cs+ and TDS=7 000 mg/L was prepared and used to evaluate the performance of the device. The results showed that the total decontamination factor(DF) of the device for Co2+,Sr2+ and Cs+ were 1.19×105,1.02×105 and 7.30×103,respectively. The combined decontamination factor of the device for the three nuclides was 1.74×104,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.

Key words: radioactive wastewater, mobile device, nuclear power plant accident, emergency treatment

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 m3/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Co2+、Sr2+、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Co2+、Sr2+、Cs+的总去污因子(DF)分别为1.19×105、1.02×105、7.30×103,对3种核素的综合去污因子为1.74×104,3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。

关键词: 放射性废水, 移动式装置, 核电站事故, 应急处理

CLC Number: