DocumentCode
3772845
Title
Counting neutrons from the spontaneous fission of 238U using scintillation detectors and mixed field analysers
Author
Helen M. O´D. Parker;Malcolm J. Joyce;Ashley Jones
Author_Institution
Department of Engineering, Lancaster University, Lancaster, LA1 4YU, UK
fYear
2015
fDate
4/1/2015 12:00:00 AM
Firstpage
1
Lastpage
5
Abstract
It is well documented that 238U 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 238U. 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.
Keywords
"Neutrons","Detectors","Photonics","Liquids","Uranium","Nuclear fuels"
Publisher
ieee
Conference_Titel
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2015 4th International Conference on
Type
conf
DOI
10.1109/ANIMMA.2015.7465617
Filename
7465617
Link To Document