辐照后核燃料中镅的放化分析

RADIOCHEMICAL ANALYSIS OF Am IN IRRADIATED FUEL

一、前言在我们另一份工作中已较详细地研究了Am与辐照核燃料溶解液中U,Np,Pu及主要裂片元素的分离条件,建立了HDEHP苹淋树脂色谱法的预分离程序。本文研究了在预分离后进一步纯化镅的条件并实测了一根辐照元件各切片中^(241)Am的含量。由于料液中Am的含量很小,所以预分离程序对^(95)Zr-^(95)Nb,^(106)Ru,^(90)Sr的去污仍不够好,而且预分离后的含Am溶液中含有大量的DTPA、乳酸等,对α测量有影响。

A method for the determination of Am in irradiated fuel is reported. Afterpreliminary separation by HDEHP Levextrel. Am is separated and purified bysynergistic extraction with 0.05 mol/l PMBP-0.25 mol/l TBP. A stable chemicalyield of (95.6±0.6)% for Am is obtained. The decontamination factors for U,^(239)Pu are all over 10~6 and those for ^(95)Zr-^(95)Nd, ^(144)Ce and ^(147)Nd all over 10~4; for^(90)Sr over 10~5; for ^(137)Cs over 10~6.