γ-ray spectrometry on nuclear material using a CdZnTe detector

A planar CdZnTe detector of dimensions of 10 × 10 × 5 mm was tested for its application to γ-ray spectrometry on nuclear material. The outcome from the analysis of a spent nuclear fuel pin, natural uranium solutions, plutonium powder and mixed oxide pellet (MOX) are reported. Quantification could be performed on the specra obtained from samples containing only uranium. However, on the basis of the spectra obtained, it was found possible to qualitatively discriminate between the different kinds of nuclear material analysed.