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A. Morgenstern, C. Apostolidis, H. Ottmar, K. Mayer

Analysis of ²³⁷Np in spent fuel solutions

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.

Radiochimica Acta, Oldenbourg Wissenschaftsverlag

Print ISSN: 0033-8230
Volume: 90, 07/2002
Pages: 389

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