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文章描述了燃料元件制造厂可燃含铀废物的γ扫描装置和无损分析（ＤＮＡ）刻度方法。采用４个高效率ＮａＩ（Ｔ１）探头系统对已包装的废物进行旋转γ扫描。系统包括多路讯号线性混合、多道缓冲存贮和计算机获取和能谱处理硬件和软件。当废物包中￣（２３５）Ｕ的含量为０．１０５ｇ时，１８５ｋｅＶ峰面积与本底面积之比为０．４１。１０ｍｉｎ测量灵敏度计算值为１０ｍｇ￣（２３５）Ｕ。在１－２６．４ｇ￣（２３５）Ｕ动态范围内，１０ｍｉｎ测量峰面积的相对标准偏差好于１．５％，并具有计数率、废物内γ射线自吸收和铀效率刻度曲线的微小非线性等效应自动校正功能。在刻度过程中，软件系统能够对介质密度校正曲线和铀效率刻度曲线进行拟合计算。
The article describes a γ-scanning device and a non-destructive analysis (DNA) scale method for flammable uranium-containing waste at a fuel cell manufacturer. The packaged wastes were gamma-scanned with four highly efficient Na (T1) probe systems. The system consists of multiplexed signal linear mixing, multi-buffer storage and computer acquisition and spectrum processing hardware and software. When the content of ~ (235) U in the waste package is 0.105 g, the ratio of the 185 keV peak area to the background area is 0.41. The calculated sensitivity of the measurement is 10 mg ~ (235) U. The relative standard deviation (RSD) of the peak area measured at 10 min in the dynamic range of 1-26.4 g to (235) U is better than 1.5% with a slight non-linearity of count rate, gamma ray self-absorption in waste and uranium efficiency scale curve Equivalent to automatic correction function. During the calibration process, the software system can calculate the calibration curve of medium density and the calibration curve of uranium efficiency.