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铀尾矿废石场辐射安全分析与评价 被引量:4

Radioactive Safety Analysis and Assessment of Waste Rock Pile Site in Uranium Tailings
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摘要 本文从理论计算和现场实测入手,分析了铀尾矿废石场放射性核素的分布、排放量,指出氡是铀尾矿废石场中的主要核素,是公众剂量的主要贡献者.理论计算和实测表明,随着离铀尾矿废石场距离的增加,周围环境空气中氡浓度、氡所致个人剂量呈下降趋势.本文通过对5个铀尾矿废石场的实测,提出了铀尾矿废石场防护距离的确定方法,给出了铀尾矿废石场的安全防护距离,用以指导铀尾矿废石场辐射安全防护的验证和设计工作. Based on theoretical calculation and in - situ test results, distribution and emissions of radioactive nuclides of uranium tailings impoundment and waste rock pile sites are analyzed in this paper. It is pointed out that ^222 Rn is the main nuclide of uranium tail- ings impoundment and waste rock pile site. Also ^222Rn is the main source term of public dose. ^222Rn concentrations in the atmospheric environment around and individual dose to Rn gradually decrease with increasing distances to uranium waste rock pile site. Based on in - situ tests on five uranium tailings tailings impoundment and impoundment and waste rock pile sites, a decisive method and safety protection distance are presented, which can be used to guide the validation and design of radioactive safety protection in uranium tailings impoundment and waste rock pile sites.
出处 《南华大学学报(自然科学版)》 2007年第2期24-28,共5页 Journal of University of South China:Science and Technology
关键词 铀尾矿 废石场 辐射 防护距离 uranium tailings impoundment waste rock pile radiation radon protectiondistance
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