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Counting neutrons from the spontaneous fission of 238-U using scintillation detectors and mixed field analysers

Research output: Contribution to conference - Without ISBN/ISSN Conference paper

Published
Publication date22/05/2015
<mark>Original language</mark>English
EventANIMMA - Advancements in Nuclear instrumentation Measurement Methods and their Applications - Lisbon Congress Centre, Lisbon, Portugal
Duration: 20/04/201524/04/2015

Conference

ConferenceANIMMA - Advancements in Nuclear instrumentation Measurement Methods and their Applications
CountryPortugal
CityLisbon
Period20/04/1524/04/15

Abstract

It is well documented that 238-U decays by spontaneous fission, and that it is the main component of most nuclear fuels. As nuclear fuels are largely classed as Special Nuclear Material (SNM), they have to be fully accounted for by owners and processing facilities. One possible method for verifying declared amounts of SNM is to count the spontaneous neutrons produced from 238-U. Using four EJ-309 liquid scintillation detectors and a mixed field analyser, spontaneous neutrons from 16.4 g of depleted uranium (0.3% enrichment) have been assayed. The assay method shows promising results and this proof of principle will be researched further in order for it to be applied in an industrial setting.

Bibliographic note

Presented on 22/05/2015