Please use this identifier to cite or link to this item: http://hdl.handle.net/1942/41831
Title: Gamma radiation effects on AG MP-50 cation exchange resin and sulfonated activated carbon for bismuth-213 separation
Authors: Zhu, Hongshan
Heinitz, Stephan
Eyley, Samuel
Thielemans, Wim
DERVEAUX, Elien 
ADRIAENSENS, Peter 
Binnemans, Koen
MULLENS, Steven 
Cardinaels, Thomas
Issue Date: 2023
Publisher: ROYAL SOC CHEMISTRY
Source: RSC Advances, 13 (44) , p. 30990 -31001
Abstract: Medical 225Ac/213Bi radionuclide generators are designed to provide a local supply of the short-lived 213Bi for cancer treatment. However, radiation-induced damage to the sorbents commonly used in such radionuclide generators remains a major concern. In this study, the effects of gamma radiation on AG MP-50 cation exchange resin and sulfonated activated carbon (SAC) were studied by analyzing the changes in the morphological characteristics, functional groups, and the La3+/Bi3+ sorption performance, with La3+ being a suitable non-radioactive substitute for Ac3+. The surface sulfonic acid groups of AG MP-50 resin suffered from severe radiation-induced degradation, while the particle morphology was changed markedly after being exposed to absorbed doses of approximately 11 MGy. As a result, the sorption performance of irradiated AG MP-50 for La3+ and Bi3+ was significantly decreased with increasing absorbed doses. In contrast, no apparent changes in acquired morphological characteristics were observed for pristine and irradiated SAC based on SEM and XRD characterization. The surface oxygen content (e.g., O-C00000000000000000000000000000000111111110000000011111111000000000000000000000000O) of irradiated SAC increased for an absorbed dose of 11 MGy due to free radical-induced oxidation. The sorption performance of pristine and irradiated SAC materials for La3+ and Bi3+ remained generally the same at pH values of 1 and 2. Furthermore, the applicability of AG MP-50 and SAC in the 225Ac/213Bi generators was illustrated in terms of their radiolytic stability. This study provides further evidence for the practical implementation of both AG MP-50 and SAC in 225Ac/213Bi radionuclide generators. New sulfonated activated carbon (SAC) materials were designed and synthesized for use in medical 225Ac/213Bi radionuclide generators. Their stability towards gamma radiation was assessed and compared with the commonly used AG MP-50 resin.
Notes: Cardinaels, T (corresponding author), Belgian Nucl Res Ctr SCK CEN, Inst Nucl Mat Sci, Boeretang 200, B-2400 Mol, Belgium.; Cardinaels, T (corresponding author), Katholieke Univ Leuven, Dept Chem, Celestijnenlaan 200F,PO 2404, B-3001 Leuven, Belgium.
thomas.cardinaels@sckcen.be
Document URI: http://hdl.handle.net/1942/41831
e-ISSN: 2046-2069
DOI: 10.1039/d3ra06130b
ISI #: 001087866600001
Rights: 2023 The Author(s). Published by the Royal Society of Chemistry. Open Access Article. Published on 24 October 2023. Downloaded on 11/16/2023 12:18:19 PM. This article is licensed under a Creative Commons Attribution-NonCommercial 3.0 Unported Licence.
Category: A1
Type: Journal Contribution
Appears in Collections:Research publications

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