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作 者:吕峰[1] 曹斌[1] 辛标 张文良[1] 吴昕[1] 谭亚军[1] 吕钊[1] 李泽[1] 朱荣保[1]
机构地区:[1]中国原子能科学研究院放射化学研究所
出 处:《原子能科学技术》1998年第5期445-450,共6页Atomic Energy Science and Technology
摘 要:叙述了用于非破坏分析残渣和废物中的铀、钚含量的分段γ扫描自吸收校正法(简称分段γ扫描法)。研究了分段γ扫描测量核工厂实物盘点中含铀、钚各类非均匀样品的刻度方法,分析了各种测量条件对γ自吸收校正及测量结果的影响。本方法与化学破坏分析法进行了比对分析,结果表明分段γ扫描自吸收校正法与化学破坏分析法的偏差为-3.6%,在分析误差范围内符合得很好。本分析方法成功地应用于核工厂实物盘点现场分析,测量了4类中低密度含铀、钚的残渣和废物样品,测量结果的不确定度为5%。A method of the correction for sample self attenuation used in segented gamma scanner(SGS) is described. The method of calibration for assaying the uranium and plutonium contents of each category of heterogeneous process residues and wastes in nuclear facilities is studied. The effect of variable measurement parameter on measurement results is also studied. The measurement results of SGS assay is compared with that of the destructive assay(DA), which is aimed at evaluating SGS method for assaying uranium and plutonium content in process residues and wastes. The deviation of two assay results is 3 6 %. The SGS assay results and DA assay results both are coincided well in error limits.Four category of heterogeneous process residues and wastes in nuclear facilities have assayed successfully in physical inventory. The uncertainty of measurement results for uranium and plutonium content in process residues and wastes is 5 % with 68 3 % of confidence level.
关 键 词:无损分析 分段γ扫描 核材料管理 核废物 铀 钚
分 类 号:TL271[核科学技术—核燃料循环与材料] TL273
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