文献类型：期刊文献

中文题名：原位合成四氧化三锰处理模拟核电厂含Co^(2+)放射性废水

英文题名：Treatment of Simulated Radioactive Wastewater Containing Co^(2+) in Nuclear Power Plant by In-situ Synthesis Process of Mn_3O_4

作者：詹瑛瑛[1];张禛[1];蒋博博[1];黄光团[1]

机构：[1]华东理工大学资源与环境工程学院,上海200237

年份：2016

卷号：42

期号：2

起止页码：210

中文期刊名：华东理工大学学报（自然科学版）

外文期刊名：Journal of East China University of Science and Technology

收录：CSTPCD;;Scopus;北大核心:【北大核心2014】；CSCD:【CSCD2015_2016】；

语种：中文

中文关键词：原位合成;四氧化三锰;放射性废水;正交试验;Co2+

外文关键词：in-situ synthesis;Mn3O4;radioactive wastewater;orthogonal experiment;cobalt ion

摘要：在硼酸体系中,以59Co作为模拟非放射性同位素研究了原位合成四氧化三锰处理模拟核电厂放射性废水中Co^(2+)的工艺条件。考察了反应时间、n(Mn^(2+))∶n(Co^(2+))、空气流量、反应温度以及pH对出水Co^(2+)质量浓度的影响,并由正交试验L9(43)优化工艺条件。研究表明:在废水Co^(2+)初始质量浓度10mg/L,硼酸质量浓度(以B计)1 000mg/L条件下,最佳工艺条件为反应时间105min、n(Mn^(2+))∶n(Co^(2+))=25∶1、空气流量0.7L/min、反应温度65℃以及pH 10.5,在此条件下出水Co^(2+)质量浓度约为5.68ng/L,去除效率大于99.99%,产物经XRD分析证明沉渣为Mn3O4和CoMn2O4混合物。
Using 59 Co as the simulated radioactive isotopes,the removal of Co2＋from the simulated radioactive wastewater with boric acid in nuclear power plant by in-situ synthesis of Mn3O4 was studied.The effects of reaction time,n（Mn2＋）∶n（Co2＋）,air flow,reaction temperature and pH on the Co2＋concentration in the effluent were investigated.An orthogonal experiment table L9（43）was used to optimize the process parameters.When the wastewater contained 10mg/L Co2＋and 1 000mg/L boric acid（as B）,the optimal process was as follows：the reaction time 105 min,n（Mn2＋）∶n（Co2＋）=25∶1,air flow0.7L/min,reaction temperature 65 ℃ and pH 10.5.Under the optimal condition,the effluent concentration of Co2＋was 5.68ng/L,the removal rate was more than 99.99%.XRD analysis proved that the sediment was the mixture of Mn3O4 and CoMn2O4.