Hexavalent Americium Recovery Using Copper(III) Periodate

被引:46
作者
McCann, Kevin [1 ]
Brigham, Derek M. [2 ]
Morrison, Samuel [3 ]
Braley, Jenifer C. [1 ]
机构
[1] Colorado Sch Mines, 1500 Illinois St, Golden, CO 80401 USA
[2] Oak Ridge Natl Lab, 1 Bethel Valley Rd, Oak Ridge, TN 37830 USA
[3] Pacific Northwest Natl Lab, 902 Battelle Blvd, Richland, WA 99352 USA
关键词
NITRIC-ACID; EXTRACTION; SEPARATION; OXIDATION; COMPLEXATION; ACTINIDE; KINETICS; BEHAVIOR; THORIUM; URANIUM;
D O I
10.1021/acs.inorgchem.6b02120
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
Separation of americium from the lanthanides is considered one of the most difficult separation steps in closing the nuclear fuel cycle. One approach to this separation could involve oxidizing americium to the hexavalent state to form a linear dioxo cation while the lanthanides remain as trivalent ions. This work considers aqueous soluble Cu3+ periodate as an oxidant under molar nitric acid conditions to separate hexavalent Am with diamyl amylphosphonate (DAAP) in n-dodecane. Initial studies assessed the kinetics of Cu3+ periodate autoreduction in acidic media to aid in development of the solvent extraction system. Following characterization of the Cu3+ periodate oxidant, solvent extraction studies optimized the recovery of Am from varied nitric acid media and in the presence of other fission, product, or fission product surrogate, species. Short aqueous/organic contact times encouraged successful recovery of Am (distribution values as high as 2) from nitric acid media in the absence of redox active fission products. In the presence of a post-plutonium uranium redox extraction (post-PUREX) simulant aqueous feed, precipitation of tetravalent species (Ce, Ru, Zr) occurred and the distribution values of Am-241 were suppressed, suggesting some oxidizing capacity of the Cu3+ periodate is significantly consumed by other redox active metals in the simulant. The manuscript demonstrates Cu3+ periodate as a potentially viable oxidant for Am oxidation and recovery and notes the consumption of oxidizing capacity observed in the presence of the post-PUREX simulant feed will need to be addressed for any approach seeking to oxidize Am for separations relevant to the nuclear fuel cycle.
引用
收藏
页码:11971 / 11978
页数:8
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