In situ gamma spectroscopy of spent nuclear fuel using a CdTe detector
In this paper 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 CdTe crystal was constructed and installed inside the beta-gamma hot cell. It provided effective shielding for the crystal against the intense background. Gamma spectra, with an energy resolution (full width at half maximum (FWHM)) of 7.2 keV at 662 keV, were obtained in 600 s counting time, which would allow 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.
Bibliographic Reference: Article: Nuclear Instruments and Methods A (1996)
Record Number: 199611073 / Last updated on: 1996-09-30
Original language: en
Available languages: en