A reverse 230U/226Th radionuclide generator for targeted alpha therapy applications

Mastren, Tara; Akin, Andrew C.; Copping, Roy; Brugh, Mark; Wilbur, D. Scott; Birnbaum, Eva R.; Nortier, F.M.; John, Kevin D.; Fassbender, Michael E.

doi:10.1016/j.nucmedbio.2020.09.006

Cited by 10 publications

(15 citation statements)

References 29 publications

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“…Due to the two-column scheme of 226 Th production, the proposed generator provided deep purification 226 Th from 230 U. It was found that the 230 U impurity in the 226 Th eluates did not exceed 0.01%, which was at least one order of magnitude better in comparison with the literature data reported [14].…”

Section: Long-term Performance Of Two-column 230 U/ 226 Th Generatormentioning

confidence: 62%

“…Then, having the column been washed with 7 М HCl solution, U(VI) and a part of Nb(V) were desorbed with 0.1 М HCl solution. The desorbate was adjusted to 3 M HCl by adding concentrated hydrochloric acid; and, following the known procedure [14,40], this solution was passed through a column filled with 1 mL of DGA Resin. The uranium fraction was adsorbed while the 95 Nb was washed out of the column.…”

Section: Target Preparation and Irradiation And 230 U Isolationmentioning

confidence: 99%

“…Scientific organizations worldwide are actively developing the production of 230 U through irradiation of 232 Th with protons [10][11][12][13][14]. This method has proven to be the most effective in terms of product yield compared with the reactions with deuterons [15,16].…”

Section: Introductionmentioning

confidence: 99%

“…the parent 230 U is not fixed on the column filled with sorbent while the daughter 226 Th remains adsorbed. An extraction chromatographic DGA Resin containing diglycolamide derivative is reported to be appropriate for obtaining 226 Th in citric buffer solution that is amenable to direct labeling with minimal losses of time [14]. However, the 226 Th eluate recovered from the reported reverse 230 U/ 226 Th generator contains at least 0.2% of 230 U [14], which is unacceptable for clinical trials so far.…”

Section: Introductionmentioning

confidence: 99%

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Rapid EElution of 226Th from a Two-Column 230U/226Th Generator with Diluted and Buffer Solutions

Ermolaev¹,

Skasyrskaya²,

Vasiliev³

2023

Preprint

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A unique two-column 230U/226Th generator has been developed. The focus was hold on obtaining 226Th of high purity in a solution amenable to further labeling. The first column of the proposed generator filled with TEVA Resin held 230U, from which 226Th was eluted with 7 M HCl solution. UTEVA Resin pretreated with nitric acid solution was used as a sorbent for the second column for thorium retention. 226Th was extracted with 0.01-0.05 M citric buffer solution. One cycle of generator milking took 5-7 minutes and produced > 90% of 226Th in 1.5 ml of eluate, pH 4.5-5.0. The proposed two-column 230U/226Th generator was tested over two months including a second loading of 230U additionally accumulated from 230Pa. The 230U impurity in 226Th eluate was less than 0.01% allowing to use it directly in synthesis of radiopharmaceutical compounds.

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Section: Long-term Performance Of Two-column 230 U/ 226 Th Generatormentioning

confidence: 62%

Section: Target Preparation and Irradiation And 230 U Isolationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Rapid EElution of 226Th from a Two-Column 230U/226Th Generator with Diluted and Buffer Solutions

Ermolaev¹,

Skasyrskaya²,

Vasiliev³

2023

Preprint

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“…A reverse 230 U/ 226 Th generator approach 14 was also developed using a DGA column in which 230 U/ 226 Th parent−daughter solutions were loaded onto the DGA column in >6 M HCl, followed by the elution of the parent 230 U first with 0.1 M HNO 3 and then the daughter 226 Th with a 0.1 M citrate buffer at pH 5. A small amount of 230 U parent contamination (∼0.2%) was reported in the 226 Th fraction, which may pose a problem for clinical trials.…”

Section: ■ Introductionmentioning

confidence: 99%

Simultaneous Separation of Protactinium-230 and Uranium-230 Isotopes from a Proton-Irradiated Thorium Matrix

Du,

Dyer,

Thakur

2024

Anal. Chem.

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The use of radioisotopes in cancer therapy is becoming increasingly important. As a potential candidate for targeted alpha therapy, 230 U (t 1/2 = 20.8 d), the decay daughter of 230 Pa (t 1/2 = 17.4 d) is currently being investigated for cancer treatment. For radioisotopes to be used in biomedicine, they must be radiochemically pure and free from carrier interference. This can be challenging given their short half-life. Thus, radiological separation methods for harvesting isotopes for use in biomedicine must be simple, fast, and capable of obtaining the required purity levels. Herein, we demonstrate a new rapid method for the separation of 230 U and 230 Pa from a proton-irradiated 232 Th metal target and from coproduced fission products with high recovery and purity. A dual-column approach was used, in which the first column was an anion exchange (AX) column and the second column was a DGA column. The MP-1 AX resin was used for the primary separation of the three major components (U, Pa, and Th, as well as fission products), and the DGA column was used for further purification of the separated 230 U. The method is simple and allows for straightforward separation of U, Pa, Th, and fission products; also, the entire process from target dissolution to shipment of 230 U could be completed in 3 days with an overall 230 U recovery yield of 96 ± 3%. Additionally, separated 230 Pa fractions can be used to harvest ingrown 230 U after initial separation.

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225Aс/213Bi generator for direct synthesis of 213Bi-labeled bioconjugates

Ermolaev,

Vasiliev,

Skasyrskaya

et al. 2025

Nuclear Medicine and Biology

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A reverse 230U/226Th radionuclide generator for targeted alpha therapy applications

Cited by 10 publications

References 29 publications

Rapid EElution of <sup>226</sup>Th from a Two-Column <sup>230</sup>U/<sup>226</sup>Th Generator with Diluted and Buffer Solutions

Rapid EElution of <sup>226</sup>Th from a Two-Column <sup>230</sup>U/<sup>226</sup>Th Generator with Diluted and Buffer Solutions

Simultaneous Separation of Protactinium-230 and Uranium-230 Isotopes from a Proton-Irradiated Thorium Matrix

225Aс/213Bi generator for direct synthesis of 213Bi-labeled bioconjugates

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