Gamma-Ray Spectrometry on Nuclear Material Using a CdZnTe Detector
A planar CdZnTe detector of dimensions 10x10x5 mm was tested for its application to gamma spectrometry on nuclear material. The outcome from the analysis of a spent fuel pin, natural uranium solutions, plutonium powder and mixed oxide pellet (MOX) are reported. Quantification could be performed on the spectra obtained from samples containing only uranium. However, on the basis of the spectra obtained, it was found possible to quantitatively discriminate between the different kinds of nuclear material analysed.
ABBAS Kamel;
NICOLAOU George;
SCHWALBACH P.;
KOCH Lothar Winfried;
1996-08-09
JRC13222
https://publications.jrc.ec.europa.eu/repository/handle/JRC13222,
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