Journal
APPLIED RADIATION AND ISOTOPES
Volume 68, Issue 1, Pages 1-4Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.apradiso.2009.07.024
Keywords
(n, gamma)Mo-99; Tc-99m/Mo-99 solvent extraction generator; Methyl ethyl ketone; Purification; Alumina column chromatography; Na[Tc-99m]TcO4
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Funding
- Director Variable Energy Cyclotron Centre (VECC), Kolkata
- Chief Executive, Board of Radiation and Isotope Technology (BRIT)
- Head, Regional Centre, Board of Radiation and Isotope Technology (BRIT), Kolkata
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A simple and inexpensive method of separation of Tc-99m from Mo-99 produced by neutron activation of Mo-99 via the Mo-99(n,gamma)Mo-99 nuclear reaction is described. The recovery of Tc-99m was performed by solvent extraction technique followed by column (active alumina) chromatography. The overall radiochemical yield for the complete separation of Tc-99m was 85-95% (n = 10). The separated Na[Tc-99m]TcO4 was of high radionuclidic, radiochemical, and chemical purities. The method can be adopted for routine use of Tc-99m in hospital radio-pharmacies utilizing low-medium specific activity (n,gamma)Mo-99 produced in a research reactor. (C) 2009 Elsevier Ltd. All rights reserved.
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