Preemptive denaturing of 233U for more secure 225Ac production

<ns7:p> The nuclide <ns7:sup>225</ns7:sup> Ac is an alpha-emitting nuclide that can be used in targeted alpha therapy. The main production method for <ns7:sup>225</ns7:sup> Ac is the decay of <ns7:sup>233</ns7:sup> U produced by the neutron irradiation of <ns7:sup>232</ns7:sup> Th. Isotopically pure <ns7:sup>233</ns7:sup> U poses proliferation concerns, so production of <ns7:sup>225</ns7:sup> Ac in relevant quantities using this method requires denaturing (down-blending) of <ns7:sup>233</ns7:sup> U with natural or depleted uranium. Denaturing can be performed preemptively by directly mixing <ns7:sup>233</ns7:sup> Pa separated from a fuel or blanket material with an unirradiated uranium solution. This method minimizes the mass of highly enriched <ns7:sup>233</ns7:sup> U in the process stream at any time. </ns7:p>

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Publication Details

Journal
Nuclear Science and Technology Open Research
Published
2025-06-16
DOI
https://doi.org/10.12688/nuclscitechnolopenres.17681.1
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00
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article

Preemptive denaturing of 233U for more secure 225Ac production

Derek A. Haas
1 links
Nuclear Science and Technology Open Research
Nuclear reactor physics and engineering
article

Preemptive denaturing of 233U for more secure 225Ac production

Derek A. Haas
article en

Abstract

<ns7:p> The nuclide <ns7:sup>225</ns7:sup> Ac is an alpha-emitting nuclide that can be used in targeted alpha therapy. The main production method for <ns7:sup>225</ns7:sup> Ac is the decay of <ns7:sup>233</ns7:sup> U produced by the neutron irradiation of <ns7:sup>232</ns7:sup> Th. Isotopically pure <ns7:sup>233</ns7:sup> U poses proliferation concerns, so production of <ns7:sup>225</ns7:sup> Ac in relevant quantities using this method requires denaturing (down-blending) of <ns7:sup>233</ns7:sup> U with natural or depleted uranium. Denaturing can be performed preemptively by directly mixing <ns7:sup>233</ns7:sup> Pa separated from a fuel or blanket material with an unirradiated uranium solution. This method minimizes the mass of highly enriched <ns7:sup>233</ns7:sup> U in the process stream at any time. </ns7:p>

Nuclear Science and Technology Open ResearchVol. 3
Openalex Percentile: Top 82%
Nuclear reactor physics and engineering
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