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dc.contributor.authorABBAS Kamelen_GB
dc.contributor.authorNICOLAOU Georgeen_GB
dc.contributor.authorPELLOTTIERO Didieren_GB
dc.contributor.authorSCHWALBACH P.en_GB
dc.contributor.authorKOCH Lothar winfrieden_GB
dc.date.accessioned2010-02-25T14:47:42Z-
dc.date.available1996-03-05en_GB
dc.date.available2010-02-25T14:47:42Z-
dc.date.issued1996en_GB
dc.date.submitted1995-11-14en_GB
dc.identifier.citationNuclear Instruments and Methods in Physics Research A vol. 376 p. 248-253en_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC12606-
dc.description.abstractThe 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.en_GB
dc.description.sponsorshipJRC.E-Institute for Transuranium Elements (Karlsruhe)en_GB
dc.format.mediumPrinteden_GB
dc.languageENGen_GB
dc.relation.ispartofseriesJRC12606en_GB
dc.titleGamma Spectrometry of Spent Nuclear Fuel Using a Miniature CdTe Detectoren_GB
dc.typeArticles in periodicals and booksen_GB
JRC Directorate:Nuclear Safety and Security

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