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IRSN, Institut de radioprotection et de sûreté nucléaire

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Enhancing Nuclear Safety


Research

Publications

Dosimetric and spectrometric neutron measurements around an annular vessel containing a plutonium nitrate fissile solution

Tourniera B., Itie C., Medioni R., Rich C., Mussoni F., Camus L., Pichenot G., Crovisier P., Cutarella D., Asselineau B., Groetz J-E. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 476(1-2), 440-445

Document type > *Article de revue

Keywords > external dosimetry, methodology, neutrons

Research Unit > LRDE (External dosimetry research laboratory)

Authors > ASSELINEAU Bruno, ITIE Christian

Publication Date > 01/01/2002

Summary

The new ICPR60 recommendations and the consideration of the ALARA principle have led the operators of nuclear facilities to evaluate with a higher care, the doses received by workers. The aim of this paper is to present a recent study concerning mixed field characterisation at a workplace located in a reprocessing laboratory. As a first step, neutron spectrum determination was achieved by two ways: simulation using MCNP code and experimental measurements with Bonner spheres and recoil proton counters. Neutron spectrum allowed the evaluation of dosimetric quantities. Measurements were then performed with different devices routinely used in radioprotection. The authors describe the measurement techniques, present the results obtained, and finally compare and discuss them. (C) 2002 Elsevier Science B.V. All rights reserved.

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