非铀矿山工作人员经由吸入途径所致内照射剂量估算方法探讨  

Estimation of internal dose with aerosol cluse inhaled by non-uranium miners

作　　者：徐翠华[1] 张庆[1] 张京[1] 赵力[1] 周强[1] 李文红[1] 任天山[1] 苏旭[1] 

机构地区：[1]中国疾病预防控制中心辐射防护与核安全医学所,北京100088

出　　处：《中华放射医学与防护杂志》2009年第2期184-187,共4页Chinese Journal of Radiological Medicine and Protection

摘　　要：目的建立我国非铀矿山工作人员经由吸入途径所致内照射年待积有效剂量的方法。方法用便携式大流量空气采样器在矿区现场采集气溶胶样品，实验室γ能谱仪测量分析样品中放射性核素含量，然后根据测量结果估算内照射年待积有效剂量。结果用此方法对云南东川铜矿现场采集的2个气溶胶样品分析了放射性活度，估算了经由吸入途径所致内照射年待积有效剂量。结论探讨了用大流量便携式空气采样器和γ能谱仪分析方法估算经吸入途径所致内照射年待积有效剂量的方法。Objective To establish a method for estimating internal dose from aerosol inhalation in nonuranium miners. Methods Aerosol samples in a tunnel in Dongchuan Copper Mine in Yunnan Province were collected by portable high flux air sampler. Radionuclides collected at the sampler filters were analyzed by the gamma spectrometry. Annual committed effective dose due to inhalation of the aerosol dust was estimated using the formula provided by ASTM. Results Radionuclides collected in two aerosol samples were anlayzed, the annual committed effective doses due to inhalation of 1 μm and 5 μm aerosol were estimated. Conclusions The method of using high flux air sampling and gamma spectrometry is explored to estimate the dose from aerosol inhalation.

关 键 词：非铀矿山 空气采样器 Γ谱仪 内照射 年待积有效剂量 

分 类 号：R144[医药卫生—公共卫生与预防医学]