Gamma Spectrometry on Nuclear Material Using a CdZnTe Detector
A planar CdZnTe detector with dimensions of 10 by 10 by 5 mm was tested for its application to gamma 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 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.
Bibliographic Reference: Article : Journal of Applied Radiation and Isotopes (1996)
Record Number: 199610770 / Last updated on: 1996-08-16
Original language: en
Available languages: en