摘要
在乏燃料后处理过程中,通常会在手套箱中处理带有强放射性的物料。为保证人员辐射安全,需要对手套箱中的源项及手套箱的辐射屏蔽进行分析,以判断可在手套箱中操作的源项总活度和各类型射线强度范围,并评估人员的操作时限。计算结果分析表明,一般情况下α粒子对手部(穿戴一定厚度且无破损的手套)和对手套箱外人体躯干的辐射可以忽略:为降低中子对人体的辐照剂量,需要控制手套箱物料中中子产额比较高的核素的含量(如Pu)和总的物料操作量;此外,还应该严格管控^(90)Sr、^(90)Y、^(137)Cs等纯β射线核素的净化效率,以有效限制β射线对手部的照射剂量和其轫致辐射产生的光子对人体的二次辐照。
In the process of spent fuel reprocessing,some materials with high activity have been treated frequently in the glove boxes.In order to ensure the worker＇s radiation safety,an analysis of glove box radiation shielding and source terms is significant to determine the total activity limit and the activity limit range of different rays while reprocessing radioactive materials in the glove boxes,so as to determine the working time limitation.A basic calculation result shows that generally alpha particles could be negligibleduring the calculation of its radiation effect on hands in unbroken gloves,which have a certain thickness,and on body outside the glove boxes.In order to reduce the radiation exposure caused by neutron,portion of nuclides such as Pu which has a high neutron yield,and also the total nuclide amount should be controlled.Nevertheless,the purification of nuclide emitting pure beta ray such as ^（90）Sr、^（90）Y、^（137）Cs should be strictly supervised in order to restrict the beta ray exposure on hands and its bremsstrahlung effect.
出处
《核安全》
2016年第2期35-40,共6页
Nuclear Safety
基金
能源局-大型核燃料后处理厂关键设备方案研究-连续环尾端方案研究子课题
项目编号2010ZX06201-01
关键词
手套箱辐射屏蔽
手部辐射剂量
轫致辐射
glove box radiation shielding
radiation dose for hands
bremsstrahlung
