林宝,孙桂湘,张超宇,等.核医学场所空气中131I浓度监测及工作人员内照射剂量评价探讨[J].中华放射医学与防护杂志,2023,43(9):717-723.Lin Bao,Sun Guixiang,Zhang Chaoyu,et al.Evaluation of internal doses to workers and monitoring of 131I concentration in air in nuclear medicine workplaces[J].Chin J Radiol Med Prot,2023,43(9):717-723
核医学场所空气中131I浓度监测及工作人员内照射剂量评价探讨
Evaluation of internal doses to workers and monitoring of 131I concentration in air in nuclear medicine workplaces
投稿时间:2023-04-25  
DOI:10.3760/cma.j.cn112271-20230425-00129
中文关键词:  131I  空气采样  活度浓度  内照射
英文关键词:131I  Air sampling  Activity concentration  Internal exposure
基金项目:河南省医学科技攻关计划项目(LHGJ20190815)
作者单位E-mail
林宝 河南省卫生健康技术监督中心, 郑州 450046  
孙桂湘 郑州市卫生计生监督局, 郑州 450053  
张超宇 河南嘉德恒立科技有限公司, 郑州 450001  
翟贺争 中国医学科学院放射医学研究所, 天津 300192  
郭勇 郑州市卫生计生监督局, 郑州 450053  
张树义 河南省卫生健康技术监督中心, 郑州 450046  
刘少龙 河南嘉德恒立科技有限公司, 郑州 450001  
郭子轩 河南嘉德恒立科技有限公司, 郑州 450001  
程晓军 河南省第三人民医院(河南省职业病医院) 河南省辐射生物与流行病学医学重点实验室, 郑州 450052 hnfsws@163.com 
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中文摘要:
      目的 了解医疗机构131I治疗工作场所空气中131I核素的活度浓度水平,探讨通过空气采样方法估算工作人员内照射剂量的方法并分析其影响因素。方法 选取郑州市10家开展131I核素治疗的工作场所,采用空气采样方法采集131I治疗工作场所中放射性气溶胶,用高纯锗γ能谱仪进行γ放射性核素测定并推算工作场所空气中131I核素的活度浓度水平,根据测量结果和现场调查结果估算放射工作人员因131I核素吸入导致的内照射剂量。结果 19个分装间空气样品的131I活度浓度为0.087~570 Bq/m3,平均为(51.04±128.58)Bq/m3;11个病房空气样品的131I活度浓度为0.162~54.6 Bq/m3,平均为(7.97±15.89)Bq/m3。根据GBZ 129-2016《职业性内照射个人监测规范》推荐的典型工作时间估算,放射工作人员由于吸入131I核素导致的年待积有效剂量范围为2 μSv~10 mSv,平均为(0.61±1.80)mSv,年有效剂量均未超过国家标准所规定的剂量限值。结论 郑州市10家医疗机构核医学工作场所中131I核素活度浓度较高的样品多分布在甲状腺癌住院患者较多、核素操作量较大的三甲医院,由此导致的工作人员内照射剂量不容忽视。根据空气样品的测量结果估算内照射剂量带有很大不确定度,但空气采样方法可及时发现异常或事故情况下的放射性污染,为工作人员开展体外直接测量和内照射评价提供预警。
英文摘要:
      Objective To asscentain the 131I activity concentration in 131I treatment workplaces and to explore the method of estimating the internal dose to workers by air sampling and to analyze its influencing factors.Methods Air sampling method was used to collect aerosols containing radioactivity in 10 randomly selected workplaces in Zhengzhou where 131I therapy was performed. Aactivity concentration of 131I in treatment workplace was measured for gamma emitters by gamma-ray spectrometry. The internal dose due to 131I inhalation was estimated based on measurement result and field investigation result. Results The activity concentration of 131I in air samples from 19 subpacking rooms ranged from 0.087 to 570 Bq/m3, with an average of (51.04 ±128.58) Bq/m3. Those from 11 wards ranged from 0.162 to 54.6 Bq/m3, with an average of (7.97 ±15.89) Bq/m3. In terms of the work hours recommended by the national standard GBZ 129-2016 Specifications for individual monitoring of occupational internal exposure, the estimated annual effective dose to radiation workers due to the inhalation of 131I ranges from 0.002 to 10 mSv, with an average of (0.61 ±1.80) mSv, below the dose limit specified in the national standards.Conclusions The samples with high 131I activity concentration in nuclear medicine workplaces of 10 medical institutions selected in Zhengzhou are mostly distributed in tertiary class hospitals operating large amount of radionuclide with large numbers of thyroid cancer patients adimitted. The result ing internal dose to radiation workers cannot be ignored. Estimating the internal dose based on the measurement result of air samples has a large uncertainty.However, air sampling method can promptly detect radioactive contamination in case of abnormal events or accidents, providing early warning for workers to carry out dose measurement from external exposure and internal exposure assessment.
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