使用镭 226 和钆 157 混合靶在核反应堆中进行锕 225 光子核生产。

IF 4.3 3区材料科学 Q1 ENGINEERING, ELECTRICAL & ELECTRONIC

ACS Applied Electronic Materials Pub Date : 2024-07-04 DOI:10.1016/j.nucmedbio.2024.108940

Artem V. Matyskin , Susanna B. Angermeier , Saleem S. Drera , Michael C. Prible , Jeffrey A. Geuther , Michael D. Heibel

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For this purpose, a target consisting of 1.4 mg of <sup>226</sup>Ra(NO<sub>3</sub>)<sub>2</sub> (T<sub>1/2</sub> = 1600 years) and 115.5 mg of 90 % enriched, stable <sup>157</sup>Gd<sub>2</sub>O<sub>3</sub> was irradiated for 48 h in the Breazeale Nuclear Reactor with an average neutron flux of 1.7·10<sup>13</sup> cm<sup>−2</sup>·s<sup>−1</sup>. Gadolinium-157 has one of the highest thermal neutron capture cross sections of 0.25 Mb, and its neutron capture results in emission of high-energy, prompt γ-photons. Emitted γ-photons interact with <sup>226</sup>Ra to produce <sup>225</sup>Ra according to the <sup>226</sup>Ra(γ, n)<sup>225</sup>Ra reaction. Gadolinium debulking and separation of undesirable, co-produced <sup>227</sup>Ac from <sup>225</sup>Ra was achieved in one step by using 60 g of branched DGA resin. 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引用次数: 0

摘要

背景：锕-225是最有希望用于α靶向治疗的放射性核素之一。其有限的可用性极大地限制了基于 225Ac 的放射性药物的临床试验和潜在应用：在这项工作中，我们研究了从核反应堆的热中子通量中产生 225Ac 的可能性。为此，我们在布雷泽尔核反应堆中用 1.7-1013 cm-2-s-1 的平均中子通量对 1.4 毫克 226Ra（NO3）2（T1/2 = 1600 年）和 115.5 毫克富集度为 90% 的稳定 157Gd2O3 靶件进行了 48 小时的辐照。钆-157 的热中子俘获截面为 0.25 Mb，是最高的热中子俘获截面之一。根据 226Ra(γ，n)225Ra 反应，发射的γ 光子与 226Ra 相互作用产生 225Ra。通过使用 60 克支化 DGA 树脂，可一步实现钆的脱钙和从 225Ra 中分离出不需要的、共生的 227Ac。225Ac 从 225Ra 中生长出来后（T1/2 = 14.8 d），使用 5 克 bDGA 树脂从 226Ra 和 225Ra 部分中提取 225Ac，然后使用 5 mM HNO3 进行洗脱：测量的 225Ac 活性表明，在轰击结束时，0.9 毫克 226Ra 产生了 6(1) kBq 或 0.16(3) μCi (1σ)的 225Ra：结论：所开发的 225Ac 分离技术是一种无废物工艺，可用于在核反应堆中获得纯 225Ac。

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Actinium-225 photonuclear production in nuclear reactors using a mixed radium-226 and gadolinium-157 target

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Actinium-225 photonuclear production in nuclear reactors using a mixed radium-226 and gadolinium-157 target

Background

Actinium-225 is one of the most promising radionuclides for targeted alpha therapy. Its limited availability significantly restricts clinical trials and potential applications of ²²⁵Ac-based radiopharmaceuticals.

Methods

In this work, we examine the possibility of ²²⁵Ac production from the thermal neutron flux of a nuclear reactor. For this purpose, a target consisting of 1.4 mg of ²²⁶Ra(NO₃)₂ (T_1/2 = 1600 years) and 115.5 mg of 90 % enriched, stable ¹⁵⁷Gd₂O₃ was irradiated for 48 h in the Breazeale Nuclear Reactor with an average neutron flux of 1.7·10¹³ cm⁻²·s⁻¹. Gadolinium-157 has one of the highest thermal neutron capture cross sections of 0.25 Mb, and its neutron capture results in emission of high-energy, prompt γ-photons. Emitted γ-photons interact with ²²⁶Ra to produce ²²⁵Ra according to the ²²⁶Ra(γ, n)²²⁵Ra reaction. Gadolinium debulking and separation of undesirable, co-produced ²²⁷Ac from ²²⁵Ra was achieved in one step by using 60 g of branched DGA resin. After ²²⁵Ac ingrowth from ²²⁵Ra (T_1/2 = 14.8 d), ²²⁵Ac was extracted from the ²²⁶Ra and ²²⁵Ra fraction using 5 g of bDGA resin and then eluted using 5 mM HNO₃.