Published March 2002 | Version v1
Report Open

Analysis of isotope ratio of 232U/233U in irradiated thoria by alpha spectrometry

  • 1. Fuel Reprocessing Div., Bhabha Atomic Research Centre, Mumbai (India)
  • 2. Power Reactor Fuel Reprocessing Plant, Bhabha Atomic Research Centre, Tarapur (India)

Description

Indian nuclear program envisages the use of vast deposits of thorium in the country at the second stage for the production of 233U, a fissile material. Among the other isotopes produced, 232U content is of greater significance to fuel reprocessors as its daughter products contribute to high leve1 of gamma dose during reprocessing. Alpha spectrometric method for the isotope ratio of 232U/233U in irradiated thoria has been successfully developed in our laboratory. The report describes the separation procedure followed using Tri-n-Octyl Phosphine Oxide (TOPO) for the purification of uranium from its daughter products and alpha spectrometric method followed for determining 232U content. Alpha spectrum evaluation is also explained in detail. Comparison of spectra from sources prepared prior and after separation forms the method for determining 228Th activity in uranium. The method is simple and fast. (author)

Availability note (English)

Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
19 p.
Report number
BARC--2002/E/007

Optional Information

Notes
12 refs., 4 figs., 3 tabs.