Journal of Radioanalytical and Nuclear Chemistry
Volume/Issue:
Volume 288: Issue 1
Reduction of 68Ge activity containing liquid waste from 68Ga PET chemistry in nuclear medicine and radiopharmacy by solidification
Authors:
Erik de Blois Department of Nuclear Medicine, Erasmus MC, ‘s Gravendijkwal 230, 3015 Rotterdam, The Netherlands

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Ho Chan Department of Nuclear Medicine, Erasmus MC, ‘s Gravendijkwal 230, 3015 Rotterdam, The Netherlands

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Kamalika Roy Department of Chemistry, University of Calcutta, Kolkata, India

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Eric Krenning Department of Nuclear Medicine, Erasmus MC, ‘s Gravendijkwal 230, 3015 Rotterdam, The Netherlands

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Wouter Breeman Department of Nuclear Medicine, Erasmus MC, ‘s Gravendijkwal 230, 3015 Rotterdam, The Netherlands

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Pages:
303–306
Online Publication Date:
22 Dec 2010
Publication Date:
01 Apr 2011
Article Category:
Research Article
DOI:
https://doi.org/10.1007/s10967-010-0915-8
Keywords:
68Ge; Waste; Sorbent; Generator
Open access

Abstract  

PET with 68Ga from the TiO2- or SnO2- based 68Ge/68Ga generators is of increasing interest for PET imaging in nuclear medicine. In general, radionuclidic purity (68Ge vs. 68Ga activity) of the eluate of these generators varies between 0.01 and 0.001%. Liquid waste containing low amounts of 68Ge activity is produced by eluting the 68Ge/68Ga generators and residues from PET chemistry. Since clearance level of 68Ge activity in waste may not exceed 10 Bq/g, as stated by European Directive 96/29/EURATOM, our purpose was to reduce 68Ge activity in solution from >10 kBq/g to <10 Bq/g; which implies the solution can be discarded as regular waste. Most efficient method to reduce the 68Ge activity is by sorption of TiO2 or Fe2O3 and subsequent centrifugation. The required 10 Bq per mL level of 68Ge activity in waste was reached by Fe2O3 logarithmically, whereas with TiO2 asymptotically. The procedure with Fe2O3 eliminates ≥90% of the 68Ge activity per treatment. Eventually, to simplify the processing a recirculation system was used to investigate 68Ge activity sorption on TiO2, Fe2O3 or Zeolite. Zeolite was introduced for its high sorption at low pH, therefore 68Ge activity containing waste could directly be used without further interventions. 68Ge activity containing liquid waste at different HCl concentrations (0.05–1.0 M HCl), was recirculated at 1 mL/min. With Zeolite in the recirculation system, 68Ge activity showed highest sorption.

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Cover Journal of Radioanalytical and Nuclear Chemistry
Journal of Radioanalytical and Nuclear Chemistry
Print ISSN:
0236-5731
Online ISSN:
1588-2780

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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)

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