ABSTRACT Cation exchange chromatography has historically been used to concentrate plutonium (Pu) solutions during spent nuclear fuel reprocessing. Over time, availability of well-characterized and well-understood resins for this niche purpose… Click to show full abstract
ABSTRACT Cation exchange chromatography has historically been used to concentrate plutonium (Pu) solutions during spent nuclear fuel reprocessing. Over time, availability of well-characterized and well-understood resins for this niche purpose has decreased. Additionally, new resin materials have come to market, necessitating a thorough evaluation of current cation exchange products for their effectiveness at concentrating Pu solutions. This study compares three commercially available 50W-X8 50–100 mesh cation exchange resins: Dowex™, AmberChrom™, and AG®. Herein, these resins are assessed for their loading capacity, uptake kinetics, and ability to concentrate dilute Pu solutions, initially using samarium (Sm) as a non-radiological surrogate. Results show no significant differences in loading capacities or uptake kinetics among the three resins for Sm. However, AmberChrom™ demonstrates slightly preferred properties, effectively concentrating a dilute Sm solution from 2.8 mM to 120 mM in a small column configuration (0.7 cm diameter). In a larger column setup (1.5 cm diameter), the AmberChrom™ 50W-X8 50–100 mesh resin concentrated a second Sm solution from 20.5 mM to 225 mM. Building on these results, the AmberChrom™ resin was then used to successfully concentrate a dilute Pu(III) solution from 20.5 mM to 221 mM with the larger column configuration. These findings highlight AmberChrom™ 50W-X8 50–100 mesh resin as a promising candidate for effective cation exchange chromatography applications in spent nuclear fuel reprocessing, particularly for concentrating dilute plutonium solutions, with the AG® resin being a close competitor.
               
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