核安全2024，Vol.23Issue(4)：26-30,5.
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
摘要
Abstract
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Key words
co-processing of cement kiln/beryl waste residue/radioactivity/limit value分类
能源科技引用本文复制引用
赵木,赵璇,安田鑫..水泥窑协同处置绿柱石废渣放射性限值研究[J].核安全,2024,23(4):26-30,5.基金项目
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) （2019YFC1907704）
