Authors:
A. Bilewicz Institute of Nuclear Chemistry and Technology Dorodna 16 03-195 Warsaw Poland

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K. Żuchowska Institute of Nuclear Chemistry and Technology Dorodna 16 03-195 Warsaw Poland

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B. Bartoś Institute of Nuclear Chemistry and Technology Dorodna 16 03-195 Warsaw Poland

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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.

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Journal of Radionalytical and Nuclear Chemistry
Language English
Size A4
Year of
Foundation
1968
Volumes
per Year
1
Issues
per Year
12
Founder Akadémiai Kiadó
Founder's
Address
H-1117 Budapest, Hungary 1516 Budapest, PO Box 245.
Publisher Akadémiai Kiadó
Springer Nature Switzerland AG
Publisher's
Address
H-1117 Budapest, Hungary 1516 Budapest, PO Box 245.
CH-6330 Cham, Switzerland Gewerbestrasse 11.
Responsible
Publisher
Chief Executive Officer, Akadémiai Kiadó
ISSN 0236-5731 (Print)
ISSN 1588-2780 (Online)