某厂废酸提钪过程核素迁移分析和辐射剂量评价  

Analysis of Nuclides Migration and Evaluation of Radiation Dose in Scandium Extraction Process From Waste Acid in a Factory

作　　者：郭庆礼[1] 王岩[1] 李先杰[1] 徐乐昌[1] 杨明理[1] GUO Qing-li;WANG Yan;LI Xian-jie;XU Le-chang;YANG Ming-li(Beijing Research Institute of Chemical Engineering and Metallurgy,CNNC,Beijing 101149,China)

机构地区：[1]核工业北京化工冶金研究院

出　　处：《铀矿冶》2019年第3期232-236,共5页Uranium Mining and Metallurgy

摘　　要：在对某厂废酸提钪过程核素迁移分析和工作场所γ剂量率和氡浓度监测的基础上,对该厂提钪过程的辐射剂量进行了评价,并提出辐射防护和环境管理整改建议。研究表明:废酸中铀、钍质量浓度分别为1.52、1.31g/L,镭-226活度浓度为801.00Bq/L;提钪后废酸中99.8%的铀迁移到一步反萃废水中,钍和镭主要共存于萃余酸中;高辐射γ剂量率集中在原料废酸罐、高位桶岗位和萃取岗位,工作人员所受年有效剂量主要来自于外照射;对公众造成的年有效剂量为0.03mSv。Through the analysis of nuclides migration in the process of scandium extraction from waste acid in a factory and the monitoring of gamma dose rate and radon concentration, the radiation dose in the process of scandium extraction in the factory was evaluated, and the suggestions of radiation protection and environmental management were put forward. The results show that the mass concentration of uranium and thorium in waste acid is 1.52, 1.31 g/L respectively and the activity concentration of radium-226 is 801.00 Bq/L. 99.8% of uranium in waste acid after scandium extraction is transferred to one-step stripping wastewater, and thorium and radium mainly coexist in the residual acid. The high dose rate of gamma radiation is concentrated in the waste acid tank of raw materials, the high drum position and the extraction position. The annual effective dose of staff is mainly from external irradiation. The annual effective dose caused by the public is 0.03 mSv.

关 键 词：钪 锆英砂 废酸 放射性核素 辐射评价 

分 类 号：TL7[核科学技术—辐射防护及环境保护] TQ134.12[化学工程—无机化工]