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Gamma-spectroscopy on nuclear material was performed using planar semiconductor detectors (CdTe, CdZnTe) operating at room temperature. Spent nuclear fuel rods and samples with plutonium and natural uranium were analysed. Quantitative spectra evaluation was possible for the spent fuel (CdTe detector) and uranium samples (CdZnTe detector). The plutonium in the MOX or powder samples was qualitatively identified by the CdZnTe detector.

Additional information

Authors: NICOLAOU G, JRC Karlsruhe (DE);ABBAS K, JRC Karlsruhe (DE);KOCH L, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: INMM Annual Meeting 1997, Phoenix (US), July 20-24, 1997
Availability: Available from (1) as paper EN 40459 ORA
Record Number: 199711084 / Last updated on: 1997-09-16
Original language: en
Available languages: en