Title: Gamma Spectrometry of Spent Nuclear Fuel Using a Miniature CdTe Detector
Citation: Nuclear Instruments and Methods in Physics Research A vol. 376 p. 248-253
Publication Year: 1996
JRC N°: JRC12606
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC12606
Type: Articles in periodicals and books
Abstract: The application of a planar miniature CdTe detector for gamma spectrometry has been tested by analysing standard radioactive sources and spent nuclear fuel. The detector was connected to a charhe loss corrector amplifier and yielded an energy resolution (FWHM) of 7.2 keV at 662 keV. The application of the CdTe detector to spent fuels resulted in gamma spectra of well resolved photopeaks for the fission products 134-Cs and 137-Cs. The ratio of the two fission products, complemented by isotopic correlations, verified the burnup of the fuel to within 10% of that declared by the operator.
JRC Directorate:Nuclear Safety and Security

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