基于俄罗斯核电站紧急情况的公众辐射防护操作干预水平评估

S. Spiridonov, R. Mikailova, S. Fesenko
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引用次数: 0

摘要

本文简要分析了核事故后急性期放射性生态状况评估和防护措施实施的指标。作者描述了国际原子能机构推荐的一种评估操作干预水平(oil)的方法,以保护公众成员。"环境剂量率"和"碘-131和铯-137浓度"指标的油是根据俄罗斯核电站的紧急情况计算的。输入的数据包括在VVER-1000、VVER-1200、RBMK-1000和BN-800反应堆的核电站中,由于基于设计和超出设计的事故而向大气释放的放射性物质的信息。超出计算出的“监测”操作干预水平,意味着超出了保护公众的剂量标准,需要实施保护措施。在保守的基础上,对每个紧急情况计算的油品进行了一般化,从而建立了一般化(统一)油品。后者的值与原子能机构建议的类似指标的值不同,这是由于钠冷却BN-800反应堆超出设计基础事故释放的放射性核素组成的特殊性质。本文以实际事故释放数据为基础,运用适当的计算工具,说明了事故发生后第一阶段建立的油品的意义。结论是,在计算俄罗斯核电厂的通用油时,有必要考虑所有类型反应堆的事故情景。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Evaluation of the operational intervention levels for radiation protection of the public based on the emergency scenarios at Russian nuclear power plants
The paper presents a brief analysis of indicators designed to assess the radioecological situation in the acute period after a nuclear accident and to apply protective measures. Authors described an approach to the evaluation of operational intervention levels (OILs) for the protection of the members of the public recommended by the IAEA. The OILs for the indicators “ambient dose rate” and “concentration of I-131 and Cs-137” have been calculated based on the emergency scenarios for Russian NPPs. The input data included the information about the radioactive releases to the atmosphere due to design-based and beyond design-based accidents at NPPs with reactors VVER-1000, VVER-1200, RBMK-1000 and BN-800. The excess in the calculated "monitoring" operational intervention levels means the exceeding the dose criteria for protecting the public, which requires the implementation of protective measures. The generalization of the OILs calculated for each emergency scenario on a conservative basis resulted in an establishment of generalized (unified) OILs. The values of the latter differ from the values of similar indicators recommended by the IAEA, which is due to the specific nature of the radionuclide composition of releases from beyond design basis accidents at sodium-cooled BN-800 reactors. The paper shows the significance of the OILs established in the first period after the accident based on data on actual accidental releases using the appropriate calculation tools. The conclusion is that it is necessary to consider accident scenarios for all types of reactors when calculating generalized OILs for Russian NPPs.
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