Analysis of Np-237 in spent fuel solutions

摘要

An experimental procedure has been developed for the analysis of neptunium in input solutions of spent nuclear fuel reprocessing. The method consists of selective chromatographic extraction of neptunium and plutonium using TEVA resin followed by determination of the ratio of [Np]/[Pu] on the column by high-resolution gamma spectrometry. Knowing the concentration of plutonium from routinely performed K-edge densitometry and X-ray fluorescence measurements, the concentration of Np can be evaluated. The method has been tested on simulated solutions and validated on spent fuel of known [Np]/[Pu] ratio. [References: 10]