摘要
本文针对我国运行核电厂常用的两种桶外γ活度测量系统(整体γ射线测量系统(IGS)和分段γ射线测量系统(SGS)),阐述了桶装放射性固体废物的活度和密度分布不均匀条件下对测量系统探测效率和不确定度的影响。现场试验及蒙特卡罗模拟计算表明,桶外γ活度测量系统基本满足电厂桶装废物γ核素活度测量要求,活度分布和密度分布导致的测量结果不确定度分别在17%和20%之内;同时应正确认识桶外γ测量方法在桶装固体废物测量中的地位及作用,针对存在的问题,提出应制定废物桶活度桶外测量方法的技术规范、保证设备的工作环境和加强人员培训。
The effect of activity and density distribution of solid radioactive waste in barrels on the detection efficiency and uncertainty of two kinds of out-of-barrel activity measurement systems,integrated gamma-ray measurement System(IGS)and segmented gamma-ray measurement system(SGS),commonly used in nuclear power plants in China is described.Field tests and Monte Carlo simulations show that the out-of-barrel gamma measurement system basically meets the requirements for activity measurement of barrelled wastes in nuclear power plants,and the uncertainty of measurement results caused by the distribution of activity and density is within 17% and 20% respectively.At the same time,the position and function of this method should be correctly understood.In view of the existing problems,it is suggested that the relevant technical specifications should be prepared,the working environment of the equipment should ensured,and the personnel training should be strengthened.
作者
雷强
刘哲
蒋婧
何玮
徐琛
郑国文
Lei Qiang;Liu Zhe;Jiang Jing;He Wei;Xu Chen;Zheng Guowen(Nuclear and Radiation Safety Center,Ministry of Ecology and Environment,Beijing,102445;Fujian Fuqing Nuclear Power Co.,Ltd.,Fuqing,Fujian,350300;China Institute of Atomic Energy,Beijing,102413)
出处
《辐射防护通讯》
2020年第3期9-14,共6页
Radiation Protection Bulletin
基金
大型先进压水堆及高温气冷堆核电站国家科技重大专项《先进压水堆便于退役的要求研究》(编号:2018ZX06002005)。
关键词
核电厂
放射性固体废物
桶外γ测量
影响因素
Nuclear power plant
Solid radioactive waste
Out-of-barrel measurement
Factors
