Alain R. Lebrun

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Cadmium zinc telluride detectors (CdZnTe) have found a wide application in non-destructive assay measurements in the IAEA’s verification practice. It is because of their form factor, usability, sensitivity and good spectral characteristics that they are extensively used for fresh and spent fuel attribute test measurements. Until now, the series of CdZnTe(More)
  • P. Dvornyak, M. Koestlbauer, +4 authors Tara Twomey
  • 2011
Measurements of Uranium enrichment in UF6 cylinders is a significant part of the IAEA Safeguards verification activities at enrichment and conversion plants. Nowadays, one of the main tools for verification of Uranium enrichment in UF6 cylinders used by Safeguards inspectors is the gamma spectroscopy system with HPGe detector cooled with liquid nitrogen.(More)
Nuclear material measurements using the ISOCS technique are playing an increasing role in IAEA verification activities. The ISOCS capabilities include: a high sensitivity to the presence of U and Pu; the ability to detect very small amounts of material; and the ability to measure items of different shapes and sizes. In addition, the numerical absolute(More)
The International Atomic Energy Agency (IAEA) has initiated a coordinated R&D programme to improve its verification methods and equipment applicable to enrichment plants. The programme entails several individual projects to meet the objectives of the IAEA Safeguards Model Approach for Gas Centrifuge Enrichment Plants updated in 2006. Upgrades of(More)
Canberra Industries has developed a specialized software package, Advanced In-Situ Object Counting System (A-ISOCS), which is based on absolute gamma-spectrometric measurements. It is intended for the verification of the quantity of nuclear materials under conditions where measurements are challenged by incomplete information on the properties of assayed(More)
Production of medical radioisotopes at the Petten Research Reactor (NL) generates residues packed in cylindrical containers involving around 450 g of irradiated HEU each. Because the chemical process selectively removes the fission products, the verification can no longer rely on observation of conventional attributes such as gamma emissions of Cs-137.
IAEA verification of the nuclear material contained in fresh nuclear fuel assemblies is usually based on neutron coincidence counting (NCC). In the case of uranium fuel, active NCC provides the total content of uranium-235 per unit of length which, combined with active length verification, fully supports the verification. In the case of plutonium fuel,(More)
As computing power has become more affordable, the use of Monte Carlo radiation transport techniques for determining the response of safeguards instrumentation has become more widespread. At the International Atomic Energy Agency (IAEA) this trend is also evident. This paper will detail some of the efforts to determine absolute calibrations for nuclear(More)
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