Radiochemical separation of <sup>161</sup> Tb from neutron irradiated Gd target by liquid-liquid extraction technique

Abstract No-carrier-added (NCA) 161 Tb, which has advisable nuclear properties to be applied for cancer radiotherapy was produced at the Egyptian Second Research Reactor (ETRR-2) by neutron irradiation of natural gadolinium target via indirect nuclear reaction. The radiochemical separation of 161 Tb from irradiated gadolinium target was investigated based on solvent extraction technique using Cyanex 302. Several separation parameters were checked and optimized. According to the obtained results, the separation process of the investigated radioisotopes proceeds in two steps. The first step is an extraction of all of them into the organic phase in which the extraction % (98 %) was optimized at pH 4, 0.15 M of Cyanex 302 and 2.5 h extraction time. Moreover, the slope analysis method confirmed the participation of 2 mol of the organic extractant for the separation of 161 Tb from irradiated gadolinium. The second step is the separation of the 161 Tb isotope that was purified by the stripping of 159 Gd with a citrate solution at pH 9, which is considered as a highly efficient and promising method for separation and purification of the two radioisotopes.

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Publication Details

Journal
Radiochimica Acta
Published
2024-09-02
DOI
https://doi.org/10.1515/ract-2024-0286
Citations
1
Primary Topic
Radiopharmaceutical Chemistry and Applications
Type
article
Field-Weighted Citation Impact
0.40
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article

Radiochemical separation of 161 Tb from neutron irradiated Gd target by liquid-liquid extraction technique

Ahmed M. Shahr El-Din, Ε. H. Borai, Mohamed A. Gizawy
1 citations
Radiochimica Acta
Radiopharmaceutical Chemistry and Applications
0.40
article

Radiochemical separation of 161 Tb from neutron irradiated Gd target by liquid-liquid extraction technique

Ahmed M. Shahr El-Din, Ε. H. Borai, Mohamed A. Gizawy
article en
1 citations

Abstract

Abstract No-carrier-added (NCA) 161 Tb, which has advisable nuclear properties to be applied for cancer radiotherapy was produced at the Egyptian Second Research Reactor (ETRR-2) by neutron irradiation of natural gadolinium target via indirect nuclear reaction. The radiochemical separation of 161 Tb from irradiated gadolinium target was investigated based on solvent extraction technique using Cyanex 302. Several separation parameters were checked and optimized. According to the obtained results, the separation process of the investigated radioisotopes proceeds in two steps. The first step is an extraction of all of them into the organic phase in which the extraction % (98 %) was optimized at pH 4, 0.15 M of Cyanex 302 and 2.5 h extraction time. Moreover, the slope analysis method confirmed the participation of 2 mol of the organic extractant for the separation of 161 Tb from irradiated gadolinium. The second step is the separation of the 161 Tb isotope that was purified by the stripping of 159 Gd with a citrate solution at pH 9, which is considered as a highly efficient and promising method for separation and purification of the two radioisotopes.

Radiochimica ActaVol. 112(12)
Egyptian Atomic Energy Authority (EG)
Clean water and sanitation
Openalex Percentile: Top 35%
Radiopharmaceutical Chemistry and Applications
0.40
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