2021
DOI: 10.1080/01496395.2021.2001531
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An overview of solvent extraction processes developed in Europe for advanced nuclear fuel recycling, Part 2 — homogeneous recycling

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Cited by 35 publications
(17 citation statements)
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“…Such a vision has boosted the development of several processes for the recovery of MAs from high-level waste, and a large number of hydrophilic and lipophilic extractants have been developed to achieve this challenging goal. …”
Section: Introductionmentioning
confidence: 99%
“…Such a vision has boosted the development of several processes for the recovery of MAs from high-level waste, and a large number of hydrophilic and lipophilic extractants have been developed to achieve this challenging goal. …”
Section: Introductionmentioning
confidence: 99%
“…This has since been attributed to the short residence time of the centrifugal contactors and the need for more contacting stages dedicated to scrubbing the solvent. 19 Most prior literature and both tests on irradiated fuel utilized 1.0 M DEHiBA; however, this concentration of DEHiBA did not achieve an organic phase loading (0.14 M for JRC test), 27 which is on par with the traditional PUREX process (0.33−0.40 M). 28 Thus, while these tests were extremely useful in the demonstration that DEHiBA is a practical extractant to use with real irradiated fuel, it would be beneficial to have a solvent formulation that allows for a higher U loading, and thus less secondary radioactive waste generation.…”
Section: ■ Introductionmentioning
confidence: 99%
“…The test at JRC had a small amount of Np in the U organic stream, and a high amount of Tc. This has since been attributed to the short residence time of the centrifugal contactors and the need for more contacting stages dedicated to scrubbing the solvent . Most prior literature and both tests on irradiated fuel utilized 1.0 M DEHiBA; however, this concentration of DEHiBA did not achieve an organic phase loading (0.14 M for JRC test), which is on par with the traditional PUREX process (0.33–0.40 M) .…”
Section: Introductionmentioning
confidence: 99%
“…Research continues to improve hydrometallurgical technologies for uranium handling. New processes and extraction systems are being developed for these purposes. One of the most promising approaches is the GANEX process, which is designed to simultaneously extract all actinides (U, Np, Pu, Am, and Cm) from nitric acid solutions of SNF providing a proliferation-resistant fuel cycle. The organic phase in such a process should possess high capacity for the macrocomponent of SNF, which is U­(VI).…”
Section: Introductionmentioning
confidence: 99%