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Purification of thorium from uranium-233 process residue

Journal Article · · Separation Science and Technology
; ; ;  [1]
  1. Oak Ridge National Lab., TN (United States)
Thorium-229 can be used to produce {sup 213}Bi. Researchers in phase 1 human trials are investigating the use of antibodies labeled with {sup 213}Bi for selectively destroying leukemia cells. Other types of cancer may potentially be treated using similar approaches. Crude {sup 229}Th was liberated from Rachig rings by sonication in 7.5 M HNO{sub 3} followed by filtration. Contaminants included significant levels of uranium, a number of other metals, and radiolytic by-products of di-(2-butyl) phosphoric acid extractant (which was used i the original separation of {sup 233}U from thorium). Thorium was selectively retained on Reillex HPQ anion-exchange resin from 7.5 M HNO{sub 3} at 65%, where U(VI), Ac(III), Fe(III), Al(III), Ra(II), and Pb(II) were eluted. Thorium and uranium isotherms on Reillex HPQ are reported. The thorium was then easily eluted form the bed with 0.1 M HNO{sub 3}. To overcome mass transfer limitations of the resin, the separation was conducted at 65 C. The resin stood up well to use over several campaigns. Other researchers have reported that HPQ has excellent radiological and chemical stability. The eluted thorium was further purified by hydroxide precipitation from the organic contaminants. This process yielded 65 mCi of {sup 229}Th.
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC05-96OR22464
OSTI ID:
354462
Report Number(s):
CONF-9710103--
Journal Information:
Separation Science and Technology, Journal Name: Separation Science and Technology Journal Issue: 6-7 Vol. 34; ISSN 0149-6395; ISSN SSTEDS
Country of Publication:
United States
Language:
English

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