Title: Spent Fuel Characterization with Small CZT Detectors
Authors: BERNDT REINHARDMORTREAU PATRICIA
Citation: NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SP vol. 564 p. 290-294
Publisher: ELSEVIER SCIENCE BV
Publication Year: 2006
JRC Publication N°: JRC31901
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC31901
Type: Articles in Journals
Abstract: CdTe detectors may be utilised as miniature instruments for the measurement of gamma spectra in safeguards applications . This is applicable for measurements both to fresh fuel and irradiated nuclear fuel. The spectrum analysis, however, is more complicated than with Ge detectors. Some reasons are: the peaks are asymmetric, the peak/Compton ratio is low, peak parameters depend on the count rate and on the properties of individual detector crystals We developed a spectrum unfolding code for spectra obtained with CdTe detectors. The code makes use of a series of pattern spectra of the individual instrument. It is applied to fission product spectra and allows the coarse characterisation of the spent fuel in safeguards inspections.
JRC Institute:Institute for the Protection and Security of the Citizen

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