水泥窑协同处置绿柱石废渣放射性限值研究  

Research on the Limit of Radioactivity of Beryl Waste Residue Co-disposed by Cement Kiln

作　　者：赵木 赵璇[2] 安田鑫 Zhao Mu;Zhao Xuan;An Tianxin(CNNC Environmental Protection Engineering Co.,Ltd.,Beijing 100083,China;Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China;China Nuclear Industry 24 Construction Co.,Ltd.,Yanjiao 101601,China)

机构地区：[1]中核环保工程设计研究有限公司,北京100083 [2]清华大学核能与新能源技术研究院,北京100084 [3]中国核工业二四建设有限公司,燕郊101601

出　　处：《核安全》2024年第4期26-30,共5页Nuclear Safety

基　　金：国家重点研发计划放射性污染金属材料协同去污解控技术及装备研究和工程示范(2019YFC1907704)。

摘　　要：本文研究了水泥窑协同处置绿柱石废渣的放射性管理限值,以实现绿柱石废渣治理过程中有效、快速分拣分类。本文通过取样监测明确可在水泥窑协同处理区域及绿柱石废渣取样分析基础上,拟合放射性核素的活度浓度和废物包表面γ剂量率之间的相互关系,计算出不大于500 nSv/h样品为可用于水泥窑协同处置的豁免水平废物。本文进行两次取样分析,验证500 nSv/h作为工程实际中无须检测便可直接认定为活度浓度不超过1 Bq/g的豁免废物放射性限值,具有重要的工程实践意义。In this paper,the limit of radioactivity of beryl waste residue in cement kiln co-processing is studied in order to realize effective and rapid sorting and classification of Beryl waste residue in the process of treatment.The correlation between activity concentration of the radionuclide and γ dose rate on the surface of the waste package was fitted on the basis of sample monitoring to identify the co-processing area of the cement kiln and sample analysis of Beryl waste residue,and the key numerical value,no more than 500 nSv/h,has been calculated as an exempted level of waste that can be used for Co-processing in cement kilns.It is of great practical significance to verify that 500 nSv/h can be regarded as an exempted waste radioactive limit with activity concentration not exceeding 1 Bq/g without detection.

关 键 词：水泥窑协同处置 绿柱石废渣 放射性 限值 

分 类 号：TL949[核科学技术—辐射防护及环境保护]