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Radiation Protection Dosimetry Advance Access originally published online on May 12, 2007
Radiation Protection Dosimetry 2007 126(1-4):74-77; doi:10.1093/rpd/ncm016
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© The Author 2007. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Design and characterisation of a pulsed neutron interrogation facility

A. Favalli* and B. Pedersen

European Commission, Joint Research Centre, Institute for the Protection and Security of Citizen, TP800, Via E. Fermi, 21020 Ispra (VA), Italy

* Corresponding author: andrea.favalli{at}jrc.it

The Joint Research Centre recently obtained a license to operate a new experimental device intended for research in the field of nuclear safeguards. The research projects currently being planned for the new device includes mass determination of fissile materials in matrices and detection of contraband non-nuclear materials. The device incorporates a commercial pulsed neutron generator and a large graphite mantle surrounding the sample cavity. In this configuration, a relatively high thermal neutron flux with a long lifetime is achieved inside the sample cavity. By pulsing the neutron generator, a sample may be interrogated by a pure thermal neutron flux during repeated time periods. The paper reports on the design of the new device and the pulsed fast and thermal neutron source. The thermal neutron flux caused by the neutron generator and the graphite structure has been characterised by foil activation, fission chamber and 3He proportional counter measurements.


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