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首页> 外文期刊>Journal of Radioanalytical and Nuclear Chemistry: An International Journal Dealing with All Aspects and Applications of Nuclear Chemistry >Initial development of an alkaline process for recovery of uranium from Mo-99 production process waste residue
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Initial development of an alkaline process for recovery of uranium from Mo-99 production process waste residue

机译：从Mo-99生产工艺废渣中回收铀的碱性工艺的初步开发

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摘要

An ammonium carbonate-based process is being developed for the recovery of uranium from the residue generated by an alkaline dissolution process used in the production of the medical isotope Mo-99. As a unique application of this dissolution medium, this is the first attempt at uranium recovery from a commercial Mo-99 production process. Dissolution parameters were optimized with unirradiated residue material and applied to irradiated residue in a small hot cell. Complete recovery of uranium from the residue was achieved with three successive ammonium carbonate/peroxide leaches with final decontamination factors ranging from low values of 1-10 (Cs-137, Ru-106, Sb-125) to infinity (lanthanides).
机译：正在开发一种基于碳酸铵的方法，用于从医学同位素Mo-99生产中使用的碱溶过程产生的残留物中回收铀。作为这种溶出介质的独特应用，这是从商业Mo-99生产工艺中回收铀的首次尝试。使用未辐照的残留物材料优化溶解参数，并将其应用于小型热室中的辐照残留物。用三个连续的碳酸铵/过氧化物浸出液从残留物中完全回收铀，最终净化系数范围从1-10（Cs-137，Ru-106，Sb-125）的低值到无穷大（镧系元素）。

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