陈超, 邵明刚, 陈春燕, 孟庆森, 涂兴明. 某城市放射性废物库退役的辐射影响评价[J]. 同位素, 2023, 36(1): 35-42. DOI: 10.7538/tws.2022.youxian.018
引用本文: 陈超, 邵明刚, 陈春燕, 孟庆森, 涂兴明. 某城市放射性废物库退役的辐射影响评价[J]. 同位素, 2023, 36(1): 35-42. DOI: 10.7538/tws.2022.youxian.018
CHEN Chao, SHAO Minggang, CHEN Chunyan, MENG Qingsen, TU Xingming. Radiation Impact Assessment of the Decommissioning of a City Radioactive Waste Storage Vault[J]. Journal of Isotopes, 2023, 36(1): 35-42. DOI: 10.7538/tws.2022.youxian.018
Citation: CHEN Chao, SHAO Minggang, CHEN Chunyan, MENG Qingsen, TU Xingming. Radiation Impact Assessment of the Decommissioning of a City Radioactive Waste Storage Vault[J]. Journal of Isotopes, 2023, 36(1): 35-42. DOI: 10.7538/tws.2022.youxian.018

某城市放射性废物库退役的辐射影响评价

Radiation Impact Assessment of the Decommissioning of a City Radioactive Waste Storage Vault

  • 摘要: 为了使城市放射性废物库退役后可无限制开放,本研究探讨废物库退役辐射影响评价的关键问题,评价人员和周围环境的辐射影响。对比源项调查和控制限值,判定污染区域;按退役实施方案得到放射性废物的产生量和整备前的活度水平;利用经验公式估算职业人员的外照射、内照射剂量,分析公众的辐射影响。选取退役要执行的放射性指标和适宜场地的控制限值,提出退役施工中实现废物最小化的具体措施。经估算得到退役实施的最大个人剂量为3.9 mSv,低于剂量约束值5 mSv。剂量实测值比评价结果低约2个数量级,退役活动中工作人员受到的辐射剂量满足国家标准的要求,退役辐射环境影响在可接受范围。

     

    Abstract: In order to achieve the goal of unrestricted opening after the decommissioning of city radioactive waste storage vaults, the key problems of radiation impact assessment of the decommission of waste storage vaults were discussed and the radiation impact of personnel and surrounding environment was evaluated in this paper. The polluted area was determined by comparing the source investigation with the implemented control limits. Combined with the background level of local radiation environment and operation history, the pollution causes were analyzed. According to the decommissioning implementation scheme, the production amount of radioactive wastes and the activity level before servicing were obtained. Empirical formulas were used to estimate the external and internal radiation doses of professional personnel, and the public radiation impact was analyzed. The formulation of control limits and the acceptable level of 226Ra in the soil of the decommissioning site were discussed. The radioactive indexes for decommissioning implementation and the suitable sites control limits were selected. The specific measures to minimize waste in decommissioning construction were put forward. The maximum individual dose of decommissioning implementation was 3.9 mSv, which was lower than the dose constraint value 5 mSv. The measured dose was about 2 orders of magnitude lower than the evaluation value. The professional personnel dose in the decommissioning activities met the requirements of the national standard, and the radiation impact of decommissioning was within an acceptable range.

     

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