某厂废酸提钪过程核素迁移分析和辐射剂量评价
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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、1.31 g/L,镭-226活度浓度为801.00 Bq/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0.03 mSv。
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.
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.
引文
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[2] 刘荣丽,易师,邹龙.从氯氧化锆母液中回收钪的研究[J].矿业工程,2015,35(6):117-119.
[3] 黄奇,张月英,余守惠.从锆英石提取钪的研究[J].上海金属(有色分册),1989,10(2):36-40.
[4] IAEA.Radiation protection and NORM residue management in the zircon and zirconia industries[R].Safety Reports Series No.51.Vienna:IAEA,2007:90-95.
[5] ICRP.Scope of radiological protection control measures:ICRP publication 104[R].Amsterdam:Elsevier Ltd.,2008:76-79.
[6] 环境保护部.关于发布《矿产资源开发利用辐射环境监督管理名录(第一批)》的通知:环办[2013]12号[R].北京:环境保护部,2013.
[7] 常增有.硫酸系统锆、铪分离过程中铀、钍的回收和放射性废液的处理[J].湖南化工,1980(2):49-53.
[8] 清华大学化学化工系应用化学教研组.用溶剂萃取法分离和回收锆英石中铀的工艺研究[J].稀有金属,1981(5):8-14.
[9] 林振汉,张玲秀.用碱分解锆英砂制备ZrO2工艺中放射性的分布、处理和回收研究[J].稀有金属快报,2007,26(1):106-114.
[10] 郭庆礼,王岩,李先杰.某厂锆英砂生产氧氯化锆过程中放射性核素的转移和辐射防护[J].辐射防护,2018,38(4):293-299.
[11] 张爱莲.氯氧化锆生产废水的利用[J].河南化工,2006,23(2):35-36.
[12] 罗新文,罗方承,吴江.氯氧化锆生产过程的污染治理[J].中国材料进展,2009,28(3):58-60.
[13] 罗方承,吕文光.锆化合材料应用现状及其展望[J].化工进展,2002,21(3):196-199.
[14] 国家环境保护总局.中国环境天然放射性水平[M].北京:中国环境出版社,1995:28.
[15] 中华人民共和国国家质量监督检验检疫总局.电离辐射防护与辐射源安全基本标准:GB18871—2002[S].北京:中国标准出版社,2002:37-38.
[16] UNSCEAR.Sources and effects of ionizing radiation[R].New York:UNSCEAR,2000:92-93.