Title: Gamma-Ray Spectrometry on Nuclear Material Using a CdZnTe Detector
Authors: ABBAS KamelNICOLAOU GeorgeSCHWALBACH P.KOCH Lothar winfried
Citation: Applied Radiation and Isotopes vol. 47 no. 8 p. 755-760
Publication Year: 1996
JRC N°: JRC13222
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC13222
Type: Articles in periodicals and books
Abstract: 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.
JRC Directorate:Nuclear Safety and Security

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