IN-SITU GAMMA-SPECTROSCOPY OF SPENT NUCLEAR-FUEL USING A CDTE DETECTOR

Authors
ABBAS K NICOLAOU G KOCH L
Citation
K. Abbas et al., IN-SITU GAMMA-SPECTROSCOPY OF SPENT NUCLEAR-FUEL USING A CDTE DETECTOR, Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 383(2-3), 1996, pp. 601-604
Citations number
6
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
383
Issue
2-3
Year of publication
1996
Pages
601 - 604
Database
ISI
SICI code
0168-9002(1996)383:2-3<601:IGOSNU>2.0.ZU;2-O
Abstract
Gamma spectroscopy using a room temperature CdTe detector has been car ried out in the proximity of a spent nuclear fuel rod. In this context , a compact and transportable monitor, incorporating a planar CdTe cry stal was constructed and installed inside the beta-gamma hot cell. It provided effective shielding for the crystal against the intense backg round. Gamma spectra, with an energy resolution (FWHM) of 7.2 keV at 6 62 keV, were obtained in 600 s counting time, which would allow verifi cation of the burnup to within 10% and cooling time of the fuel to wit hin 3% of the declared values by applying specific isotopic correlatio ns. The good spatial resolution has allowed the use of the monitor as a gamma scanning device.