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Journal of Radioanalytical and Nuclear Chemistry
Authors:
A. Bilewicz
,
K. Żuchowska
, and
B. Bartoś
Abstract
An effective and simple process for the separation of 177Lu from neutron-irradiated Yb targets was developed. Irradiated Yb target was dissolved in H2SO4 solution and after reduction with sodium amalgam Yb was precipitated in the form of YbSO4. From 50 mg of Yb irradiated target only 1 mg Yb remains in solution after precipitation and separation of YbSO4. The overall recovery of 177Lu is estimated at 73%. Further efficient chromatographic separation of carrier-free 177Lu from 1 mg of Yb is relatively easy and is described in several papers.
