Abstract The recycling of minor actinides from dissolved nuclear fuels by hydrometallurgical separation is one challenging strategy for the management of spent fuel. These future separation processes will likely be based on solvent extraction processes in which an organic solvent system (extractant and diluent) will be contacted with highly radioactive aqueous solutions. To establish a separation between different elements in spent nuclear fuel, many extractants have been studied in the past. A particular example is N,N,N′,N′-tetraoctyl diglycolamide (TODGA), which co-extracts lanthanides and actinides from nitric acid solutions into an organic phase (e.g. TODGA in n-dodecane). The radiolytic stability of these extractants is crucial, since they will absorb high doses of ionizing radiation during their usage. Worldwide, different gamma irradiation facilities are employed to expose extractants to ionizing radiation and gain insight in their radiation stability. The facilities differ in many ways, such as their environment (pool-type or dry), configuration and gamma sources (often 60Co or spent nuclear fuel). In this paper, a dosimetric assessment is made using different dosimeter systems in a pool-type irradiation facility, which has the advantage to be flexible in its arrangement of 60Co sources. It is shown that Red Perspex dosimeters can be used to accurately characterize this high dose rate gamma irradiation field (approx. 13.6 kGy h−1), after comparison with alanine, Fricke and ceric-cerous dosimetry in a lower dose rate gamma irradiation field (approx. 0.5 kGy h−1). A final validation of the whole chain of techniques is obtained by reproduction of the dose constants for TODGA in n-dodecane.

中文翻译：

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用于溶剂萃取系统降解研究的伽马辐射剂量学和方法学

摘要 通过湿法冶金分离从溶解的核燃料中回收微量锕系元素是乏燃料管理的一项具有挑战性的策略。这些未来的分离过程可能基于溶剂萃取过程，其中有机溶剂系统（萃取剂和稀释剂）将与高放射性水溶液接触。为了在乏核燃料中的不同元素之间建立分离，过去已经研究了许多萃取剂。一个特殊的例子是 N,N,N',N'-四辛基二甘醇酰胺 (TODGA)，它从硝酸溶液中将镧系元素和锕系元素共萃取到有机相中（例如正十二烷中的 TODGA）。这些萃取剂的辐射稳定性至关重要，因为它们在使用过程中会吸收高剂量的电离辐射。全世界，使用不同的伽马辐照设施将萃取剂暴露于电离辐射并深入了解其辐射稳定性。这些设施在许多方面有所不同，例如它们的环境（池式或干式）、配置和伽马源（通常是 60Co 或乏核燃料）。在本文中，在池型辐照设施中使用不同的剂量计系统进行剂量测定评估，该设施的优势在于其 60Co 源的布置灵活。结果表明，在较低剂量率伽马辐射场中与丙氨酸、弗里克和铈-铈剂量测定法进行比较后，红色有机玻璃剂量计可用于准确表征这种高剂量率伽马辐射场（约 13.6 kGy h-1）。约 0.5 kGy h-1)。