USE OF MINIATURE CDZNTE X GAMMA DETECTOR IN NUCLEAR SAFEGUARDS - CHARACTERIZATION OF SPENT NUCLEAR-FUEL AND URANIUM ENRICHMENT DETERMINATION/

Authors
ABBAS K MOREL J ETCHEVERRY M NICOLAOU G
Citation
K. Abbas et al., USE OF MINIATURE CDZNTE X GAMMA DETECTOR IN NUCLEAR SAFEGUARDS - CHARACTERIZATION OF SPENT NUCLEAR-FUEL AND URANIUM ENRICHMENT DETERMINATION/, Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 405(1), 1998, pp. 153-158
Citations number
9
Categorie Soggetti
Nuclear Sciences & Tecnology","Physics, Particles & Fields","Instument & Instrumentation",Spectroscopy
Journal title
Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment → ACNP
ISSN journal
01689002
Volume
405
Issue
1
Year of publication
1998
Pages
153 - 158
Database
ISI
SICI code
0168-9002(1998)405:1<153:UOMCXG>2.0.ZU;2-4
Abstract
The feasibility to perform X/gamma-ray spectroscopy, on spent nuclear fuel and uranium solution and pellets, using a Peltier-cooled CdZnTe c rystal (9 mm(2) sensitive area, 2 mm thickness) coupled with a dedicat ed preamplifier and amplifier has been studied. In the case of spent f uel, an energy resolution of 5.6 keV at 662 keV is achieved and charac terisation of the fuel in terms of burnup and cooling time performed. The good energy resolution at low energies (1.9 keV at 122 keV) has al lowed application of the URADOS code which, on the basis of the uraniu m XKalpha-rays, determined the U-235 enrichment in the uranium solutio ns and pellets within 10% of that declared. (C) 1998 Elsevier Science B.V. All rights reserved.