我国非铀矿山工作场所γ外照射剂量估算  

Doses from external exposure at workplace in non-uranium mines in China

作　　者：张庆[1] 徐翠华[1] 张京[1] 周强[1] 赵力[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180-183,共4页Chinese Journal of Radiological Medicine and Protection

摘　　要：目的估算非铀矿山工作人员经由矿石样品外照射途径所致γ外照射年有效剂量。方法现场采集非铀矿山矿工工作场所矿石样品，利用γ能谱仪测量矿石样品中放射性核素活度浓度，进而估算采矿工作场所矿工所受年有效剂量。结果在全国7个省区13个矿区共采集、分析了32个矿石样品，其中有2种矿石活度浓度较高，所致矿工的年有效剂量超过1mSv。结论γ能谱测量分析方法可以较好地应用于非铀矿山矿石放射性核素分析，其结果可用来估算矿工所受的γ外照射剂量。Objective To estimate the dose to non-uranium miners from external exposure. Methods Ore samples of non-uranium mines were collected in site and analyzed with gamma spectrometry, then annual dose to the miners was estimated based on the measured radioactivities of radionuclides. Results Thirty-two ore samples in thirteen mines in seven provinces were collected and analyzed. Among them, radioactivity concentrations in two samples were higher than others, and the annual doses from external exposure to the radionuclides in the two ore samples were estimated to be higher than 1 mSv/a. Conclusions Gamma spectrometry is fit for determining the radionuclides concentrations and its results can be used for estimating dose from external exposure in non-uranium mines.

关 键 词：非铀矿山 γ能谱分析 γ外照射 年有效剂量 

分 类 号：R144[医药卫生—公共卫生与预防医学]