Published 2008 | Version v1
Journal article

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

  • 1. Dept. of Medical Physics, McGill Univ. Health Center, Room L5-112, Montreal, QLD H3G 1A4 (Canada)
  • 2. Radiation Biology and Health Physics Branch, Atomic Energy of Canada Limited, Chalk River Laboratories, Chalk River, ON K0J 1P0 (Canada)

Description

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 TASTRAKR, 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. (authors)

Availability note (English)

Available from doi: http://dx.doi.org/10.1093/rpd/ncn071

Additional details

Identifiers

Publishing Information

Journal Title
Radiation Protection Dosimetry
Journal Volume
130
Journal Issue
4
Journal Page Range
p. 466-475
ISSN
0144-8420

Optional Information

Notes
26 refs