A new process was developed to recover high specific activity (no carrier added) ⁹⁹Mo from electron-accelerator irradiated U₃O₈ or uranyl sulfate targets. The process leverages a novel solvent extraction scheme to recover Mo using di(2-ethylhexyl) phosphoric acid following uranium and transuranics removal with tri-n-butyl phosphate. An anion-exchange concentration column step provides a final purification, generating pure ⁹⁹Mo intended for making ⁹⁹Mo/^99mTc generators. The process was demonstrated with irradiated uranium targets resulting in more than 95% ⁹⁹Mo recovery and without presence of fission products or actinides in the product.

中文翻译：

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从用于锝 99m 发生器的低浓缩铀的加速器诱导裂变中回收高比活度钼 99

开发了一种新工艺以从电子加速器辐照的 U ₃ O ₈或硫酸铀酰靶中回收高比活度（不添加载流子）⁹⁹ Mo。该工艺利用了一种新的溶剂萃取方案使用二（2-乙基己基）磷酸以下的铀和超铀除去与三恢复沫Ñ丁基磷酸酯。阴离子交换浓缩柱步骤提供最终纯化，生成纯⁹⁹ Mo，用于制造⁹⁹ Mo/ ^99m Tc 发生器。该过程用辐照铀靶进行了证明，产生了超过 95% ⁹⁹Mo 回收并且产品中不存在裂变产物或锕系元素。