燃料元件厂可燃含铀废物γ扫描装置  

COMBUSTIBLE URANIC WASTE ASSAY SYSTEM

作　　者：朱荣保[1] 杨留成[1] 谭亚军[1] 金惠民[1] 吕钊[1] 许晓东 朴勇男 吴昕 刘建刚 

机构地区：[1]中国原子能科学研究院

出　　处：《原子能科学技术》1994年第4期308-315,共8页Atomic Energy Science and Technology

摘　　要：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。A combustive uranic waste assay system developed for nuclear fuel fabrication plant and thecalibration techniques for on-site application are described in the paper.The high efficiency detec-tion system with four NaI(T1)detectors installed at different axial positions is specially designedfor gamma ray scanning of rotating waste packages.The system employs techniques of multi-in-put of linear signals,multi-channel buffer and automatic data acquisition,system calibration anddata processing.The counting rate ratio of net peak and background at 185 keV is 0.41 for lowdensity uranic waste containing only 0.1g of ￣(235)U. The calculated detection sensitivity for 10 minassay is 10 mg of￣(235)U. The relative standard deviation of 185 keV peak area is better than ± 1.5% for assay interval of 10 min and dynamic range from 1-26.4g ￣(235)U. The capacities of datacorrections for dead time, gamma ray self-attenuation, matrix variation and non-linearity of effi-ciency calibration curve are incorporated in software.

关 键 词：含铀可燃废物 γ扫描装置 无损检验 

分 类 号：TL941[核科学技术—辐射防护及环境保护]