| 孟庆华,孔玉侠,白斌,等.某企业125I粒籽源生产过程中放射工作人员受照剂量测量与分析[J].中华放射医学与防护杂志,2025,45(1):49-55.Meng Qinghua,Kong Yuxia,Bai Bin,et al.Measurement and analysis of radiation dose for 125I seed source production radiation workers in an enterprise[J].Chin J Radiol Med Prot,2025,45(1):49-55 |
| 某企业125I粒籽源生产过程中放射工作人员受照剂量测量与分析 |
| Measurement and analysis of radiation dose for 125I seed source production radiation workers in an enterprise |
| 投稿时间：2024-01-02 |
| DOI：10.3760/cma.j.cn112271-20240102-00002 |
| 中文关键词: 125I粒籽源 放射性核素 γ能谱 外照射 内照射 |
| 英文关键词:125I seed source Radionuclide Gamma spectrometry External exposure Internal exposure |
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| 中文摘要: |
| 目的 调查某企业125I粒籽源生产过程中放射工作人员外照射和内照射剂量,为准确评价放射工作人员年受照剂量提供科学依据。方法 以某企业125I粒籽源生产现场和放射工作人员为调查对象,使用 AT1121型X、γ剂量率仪测量放射工作人员热焊、清洗粒籽源等操作点位的周围剂量当量率,估算人员所受的外照射剂量;采用LiF(Mg,Cu,P)热释光剂量计测量放射工作人员特定周期内所受外照射剂量,对两种方法获得的人员受照剂量进行对比分析。使用RG-50型空气采样器及TC-30型碘盒采集工作场所空气,用BE5030型高纯锗γ能谱仪对空气中放射性核素125I的活度浓度进行检测,估算放射工作人员内照射剂量。依据《职业性外照射个人监测规范》(GBZ 128-2019)和《职业性内照射个人监测规范》(GBZ 129-2016)等标准对人员受照剂量进行评价。结果 实测估算放射工作人员手部年受照剂量最大为24.5 mSv,各工作岗位外照射最大受照剂量为2.61 mSv/年,个人剂量监测结果最大为2.42 mSv/年,考虑到实际工作轮岗情况,与实测估算值基本一致;各工作岗位内照射所致待积有效剂量估算最大值为1.55 mSv,可达相应岗位外照射剂量估算值的17倍。结论 125I粒籽源生产过程中放射工作人员手部受照剂量较高,应有效加强手部的防护措施。同时,放射工作人员内照射剂量不可忽视,应加强场所通风,并重视规划气流流向,对场所空气中125I活度浓度进行定期监测。 |
| 英文摘要: |
| Objective To investigate the doses received by radiation workers from external and internal exposures during the production of 125I seed source, and to provide scientific basis for accurate evaluation of the annual doses of radiation workers. Methods The production site and radiation workers of a 125I seed source production enterprise were determined as the survey objects. An AT1121 X/γ dosimeter was used to measure the ambient dose equivalent rate on the operation site such as welding and cleaning of the seed source, and the dose received by workers from external exposure was estimated. LiF (Mg, Cu, P) TLD dosimeters were used to measure the external doses to workers in a specific period. The doses obtained by the two method were compared and analyzed. The RG-50 air sampler and TC-30 iodine box were used to collect the workplace air, The activity concentration of 125I in the air was measured by using of the BE5030 high-purity germanium gamma spectrometer to estimate the internal dose to workers. The evaluation of doses was performed in accordance with the national standards GBZ 128-2019 and GBZ 129-2016. Results The estimated annual dose to the worker' hands is 24.5 mSv/year. The estimated maximum dose was 2.61 mSv/year. The maximum value of individual dose monitored was 2.42 mSv/year, basically consistent with the measured value on the basis of considering the actual work rotation. The maximum estimate of committed effective dose from internal exposure was 1.55 mSv, by a factor of up to 17 times the estimated external dose at the corresponding post. Conclusions The radiation dose to the radiation workers’ hands is relatively high in the production of 125I seed source, so the protective measures for hands should be effectively strengthened. Meanwhile, the internal dose to the workers in the production process of 125I seed source should not be negelected. The ventilation of the site should be strengthened, the air flow direction should be planned, and the 125I activity concentration in the air should be regularly monitored. |
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