Use of miniature CdZnTe X/γ detector in nuclear safeguards:: characterisation of spent nuclear fuel and uranium enrichment determination

被引：11

作者：

Abbas, K

Morel, J

Etcheverry, M

Nicolaou, G

机构：

[1] Commiss European Communities, Joint Res Ctr, European Inst Transuranium Elements, D-76125 Karlsruhe, Germany

[2] CE Saclay, Lab Primaire Rayonnements Ionisants, F-91193 Gif Sur Yvette, France

来源：

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT | 1998年 / 405卷 / 01期

关键词：

X/gamma spectroscopy; nuclear material; CdZnTe detectors;

D O I：

10.1016/S0168-9002(97)01143-1

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

The feasibility to perform X/gamma-ray spectroscopy, on spent nuclear fuel and uranium solution and pellets, using a Peltier-cooled CdZnTe crystal (9 mm(2) sensitive area, 2 mm thickness) coupled with a dedicated preamplifier and amplifier has been studied. In the case of spent fuel, an energy resolution of 5.6 keV at 662 keV is achieved and characterisation of the fuel in terms of burnup and cooling time performed. The good energy resolution at low energies (1.9 keV at 122 keV) has allowed application of the URADOS code which, on the basis of the uranium XKalpha-rays, determined the U-235 enrichment in the uranium solutions and pellets within 10% of that declared. (C) 1998 Elsevier Science B.V. All rights reserved.

引用

页码：153 / 158

页数：6