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Radiation Protection Dosimetry Advance Access originally published online on March 12, 2008
Radiation Protection Dosimetry 2008 130(4):466-475; doi:10.1093/rpd/ncn071
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© The Author 2008. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Sizing particles of natural uranium and nuclear fuels using poly-allyl-diglycol carbonate autoradiography

G. Hegyi1,* and R. B. Richardson2

1 Department of Medical Physics, Room L5-112, McGill University Health Center, Montréal, Que, Canada H3G 1A4
2 Radiation Biology and Health Physics Branch, Atomic Energy of Canada Limited, Chalk River Laboratories, Chalk River, Ont, Canada K0J 1P0

* Corresponding author: mailto: gyorgy.hegyi{at}muhc.mcgill.ca

Received May 17, 2007, amended January 29, 2008, accepted February 6, 2008

Theoretical and experimental methods were developed to assess the size distribution of alpha-emitting particles captured on air-sampler filters. The particle size of oxides of low enriched, depleted and natural uranium and also aged plutonium in mixed oxide reactor fuels of known composition was determined using poly-allyl-diglycol carbonate (PADC) autoradiography, the commercial product TASTRAK®, solid-state nuclear track detectors. The exposed PADC was chemically etched to reveal clusters of tracks, radially dispersing from central points. A theoretical model was developed which converted the number of tracks in a track cluster to the hot particle diameter. The diameters of 26 particles of natural uranium oxide were measured (4–130 µm) using an optical microscope. There was a good agreement between these particle size measurements and a theoretical assessment based on the track cluster count.


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