In Situ Gamma Spectroscopy of Spent Nuclear Fuel Using a CdTe Detector.
Gamma spectroscopy using a room temperature CdTe detector has been carried out in the proximity of a spent nuclear fuel rod. In this context, a compact and transportable monitor, incorporating a planar effective shielding for the crystal against the intense background. Gamma spectra, with an energy resolution (FWHM) of 7.2 keV at 662 keV, were obtained in 600 s counting time, which would alow verification of the burnup to within 10% and cooling time of the fuel to within 3% of the declared values by applying specific isotopic correlations. The good spatial resolution has allowed the use of the monitor as a gamma scanning device.
ABBAS Kamel;
NICOLAOU George;
1996-08-13
JRC13460
https://publications.jrc.ec.europa.eu/repository/handle/JRC13460,
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