Published June 2017 | Version v1
Journal article

Evaluation of the separation and purification of 227Th from its decay progeny by anion exchange and extraction chromatography

  • 1. National Physical Laboratory, Hampton Road, Teddington, Middlesex TW11 0LW (United Kingdom)
  • 2. Chemistry Department, University of Surrey, Guildford, Surrey GU2 7XH (United Kingdom)

Description

Thorium-227 is currently undergoing evaluation as a potential radionuclide for targeted cancer therapy, and as such a high chemical purity of the material is required. To establish a reliable procedure for radiochemical isolation of 227Th from the parent 227Ac and decay progeny, which includes the radiotherapeutic 223Ra, the performance of three different separation schemes based on ion-exchange and extraction chromatography have been evaluated. The results suggest that both ion exchange and extraction chromatographic techniques can be successfully used for the separation of 227Th from its decay progeny, however extraction chromatographic resins demonstrate favourable performance in terms of Th recovery and purification from radionuclide impurities. - Highlights: • Development of a radiochemical separation of 227Th from residual 227Ac as well as from decay progeny. • Evaluation of ion-exchange and extraction chromatography techniques. • TEVA resin demonstrates favourable performance in terms of Th recovery and purification. • Developed method is applicable to both nuclear medicine and environmental analysis.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.apradiso.2017.03.020

Additional details

Identifiers

DOI
10.1016/j.apradiso.2017.03.020;
PII
S0969-8043(16)30258-5;

Publishing Information

Journal Title
Applied Radiation and Isotopes
Journal Volume
124
Journal Page Range
p. 100-105
ISSN
0969-8043
CODEN
ARISEF

Optional Information

Copyright
Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.