Abstract
New semiconductor γ-ray detectors based on CdZnTe have been developed in the last few years, and they are now being widely used. Their advantages are small size and possibility of operating without cooling. In the present work, these detectors are used to measure the radiation from spent fuel assemblies in holding ponds and dry storage sites, unirradiated nuclear materials, and radioactive wastes. The results are analyzed and compared with other types of detectors. The possible applications of CdZnTe-type detectors are determined.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
REFERENCES
G. Nicolaou, K. Abbas, and L. Koch, “The use of a CdTe detector under dry conditions of spent nuclear fuel,” in: 17th Annual Symposium of Safeguards and Nuclear Material Management, Aachen, Germany, May 9- 11, 1995, p. 519.
R. Arlt and V. Ivanov, “Advantage of using CdZnTe detectors in a system of safety measures (guarantees),” Report at a Three-Part Seminar on Measurements, Checking Various Quantities, and Estimating the Balance of Nunuclear Materials, Obninsk, Russia, October 9- 13, 2000.
V. V. Goncharov, A. M. Glukhov, P. M. Egorenko, et al., “Development of IRT-3M type fuel assemblies for pool reactors and experience in using them,” in: Proceedings of a Conference of Specialists on Exchanging Experience on Reconstruction of Research Reactors in Member Countries of COMECON, Moscow, June 22- 25, 1982.
A. V. Bushuev, V. N. Zubarev, A. F. Kozhin, et al., “Experimental-computational study of the energy-release field and burnup of IRT fuel,” At. Énerg., 88, No. 6, 426–431 (2000).
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Bushuev, A.V., Zubarev, V.N., Kozhin, A.F. et al. Possible Application of γ-Ray Spectrometers Based on CdZnTe Detectors. Atomic Energy 92, 403–407 (2002). https://doi.org/10.1023/A:1019999528118
Issue Date:
DOI: https://doi.org/10.1023/A:1019999528118