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作 者:阙骥[1] 廖运璇[1] 李小龙[1] 何玮[1] 宋凤丽[1] 吕丹[1] 赵善桂[1] 申红[1] 杨晓伟[1]
机构地区:[1]环境保护部核与辐射安全中心,北京100082
出 处:《原子能科学技术》2016年第4期751-756,共6页Atomic Energy Science and Technology
摘 要:简要介绍了DOE-STD-1027规定的非堆核设施危险分类方法,分析了其应用于核燃料循环设施时存在的问题:用于计算存量阈值的释放因子取值不具有保守性,以及剂量转换因子取自较早版本的ICRP出版物,而ICRP在后续的出版物中更新了这些因子。针对以上问题,提出了用DOE-HDBK-3010-94或NUREG/CR 6410提供的释放因子以及最新的ICRP出版物提供的剂量转换因子,修正DOE-STD-1027中危险分类放射性物质存量阈值的计算方法。采用此方法计算了采用天然铀和回收铀原料的危险2类重水堆核燃料元件制造设施与UF_6处理设施的存量阈值。The hazard classification method of nonreactor nuclear facilities in DOE-STD-1027 was outlined,and the problems were analyzed in the process of the hazard classification method used in nuclear fuel cycle facilities,which were that the release fractions were not conservative and dose conversion coefficients were outdated.A modification method was proposed,and the release fractions in DOE-HDBK-3010-94 or NUREG/CR6410 and dose conversion coefficients in latest ICRP publications were used to recalculate the thresholds in this method.Based on the new method,hazard category 2radionuclide thresholds were obtained,which are applicable to heavy water reactor nuclear fuel manufacturing facilities and UF6 handling facilities.
分 类 号:TL211[核科学技术—核燃料循环与材料] X946[环境科学与工程—安全科学]
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