接触^(131)I放射性核素工作人员内照射剂量估算方法的初步研究  

Preliminary study on assessment of internal dose to workers exposed to ^(131)I radionuclide

作　　者：黄丽华[1] 郑琪珊 张燕[1] 郑森兴[1] 魏伟奇 Huang Lihua;Zheng Qishan;Zhang Yan;Zheng Senxin;Wei Weiqi(Fujian Center of Prevention and Control of Occupational Diseases and Chemical Poisoning,Fuzhou,350025,China)

机构地区：[1]福建省职业病与化学中毒预防控制中心,福州350025

出　　处：《中华放射医学与防护杂志》2021年第12期898-905,共8页Chinese Journal of Radiological Medicine and Protection

基　　金：福建省自然科学基金(2019J01094)。

摘　　要：目的探索接触^(131)I放射性核素放射工作人员内照射剂量估算方法。方法选择某^(131)I放射性药物生产企业和某开展^(131)I甲亢和甲状腺癌治疗的医院核医学科放射工作人员,使用便携式高纯锗(HPGe)γ谱仪,以7 d为周期,连续4次测量甲状腺部位^(131)I活度,结合人员接触^(131)I的轮岗方式,估算内照射剂量。结果以监测月份为典型月份估算人员内照射剂量时,调查企业从事^(131)I放射性药物分装的生产人员年待积有效剂量为0.09~1.93 mSv,调查医院核医学科工作人员内照射年待积有效剂量为0.06~0.58 mSv。对监测结果进行校正和结合轮岗方式后估算的工作人员内照射年待积有效剂量,放射性药物生产工作人员和核医学科工作人员分别为0.06~1.22 mSv和0.03~0.16 mSv。结论在进行接触^(131)I放射性核素工作人员内照射剂量估算时,仅以单次测量的结果估算全年受照剂量会带来较大的误差。在连续监测时,应根据前续监测周期的结果对后续监测周期结果进行校正。为准确估算人员内照射剂量,应充分考虑工作人员接触^(131)I的方式、接触的时间、接触的频率、内污染的途径等因素。对于接触^(131)I内照射剂量可能>1 mSv/年的工作人员,以14 d作为常规监测周期较为适宜。Objective To explore the assessment methodology for internal dose to workers exposed to ^(131)I radionuclide.Methods Workers were chosen in a ^(131)I radiopharmaceutial manufacturer and a nuclear medicine department in a hospital using ^(131)I to treat hyperthyroidism and thyroid cancer.A portable high purity germanium(HPGe)gamma spectrometer was used to measure the content of ^(131)I in the thyroid for 4 consecutive times in a period of 7 d.The internal dose was estimated combining with the work rotation mode for workers dealing with ^(131)I.Results When the monitoring month was used as a typical month to estimate the internal dose,the annual committed effective dose was 0.09-1.93 mSv for the production staff engaged in the repackaging of ^(131)I radiopharmaceuticals in the surveyed enterprise,and 0.06-0.58 mSv for the nuclear medicine staff in the surveyed hospital.After adjusting the monitoring result of the current monitoring period based on the rotation mode,the annual committed effective dose was estimated to be 0.06-1.22 mSv for radiopharmaceutical production workers and 0.03-0.15 mSv for nuclear medicine workers,respectively.Conclusions In the assessment of internal dose to radiation workers exposed to ^(131)I,using a single time measurement result to estimate the annual dose would lead to a larger error.In the case of continuous monitoring,the result of subsequent monitoring periods should be corrected according to the result of previous monitoring periods.In order to accurately estimate the internal dose of workers exposed to ^(131)I,it is necessary to take full account of the ^(131)I exposure pattern,time and frequency and the internal contamination route.For workers who may be exposed to ^(131)I with potential internal dose greater than 1 mSv/year,a 14 day-routine monitoring period was appropriate.

关 键 词：内照射 剂量估算 核医学 ^(131)I 放射性药物生产 

分 类 号：R144[医药卫生—公共卫生与预防医学]