Thermal stability and radiation resistance of trifluoromethyl phenyl sulfone in the presence of nitric acid

Белова, Е. В.; Nazin, E. R.; Skvortsov, I. V.; Sokolov, I.P.; Rodin, A. V.; Stefanovsky, S. V.; Myasoedov, Β. F.

doi:10.1134/s1066362216050076

Cited by 7 publications

(1 citation statement)

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“…It has high thermal-, hydrolytic-, and radiolytic stability and yields a high solubility of CyMe 4 -BTBP. [39][40][41] The actinide distribution ratios are maintained at gamma doses of up to approximately 160 kGy, and the CHALMEX FS-13 solvent was shown to have higher radiolytic stability compared to the CHALMEX cyclohexanone solvent. [39,42] FS-13 itself does not extract any metals, although the solvent as a whole (CyMe 4 -BTBP, TBP, and FS-13) yields good separation factors for uranium, plutonium, and americium towards the lanthanides (i.e., europium), with extraction equilibrium reached within 20 minutes.…”

Section: Introductionmentioning

confidence: 99%

Batch Tests for Optimisation of Solvent Composition and Process Flexibility of the CHALMEX FS-13 Process

Authen

Wilden

Halleröd

et al. 2020

Solvent Extraction and Ion Exchange

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Studies have been performed with the purpose of determining the optimal solvent composition of a Chalmers grouped actinide extraction (CHALMEX) solvent for the selective coextraction of transuranic elements in a novel Grouped ActiNide EXtraction (GANEX) process. The solvent is composed of 6,6'-bis(5,5,8,8-tetramethyl-5,6,7,8-tetrahydro-benzo-[1,2,4]triazin-3-yl)-[2,2']-bipyridine (CyMe 4-BTBP) and tri-n-butyl phosphate (TBP) in phenyl trifluoromethyl sulfone (FS-13). The performance of the system has been shown to significantly depend on the ratios of the two extracting agents and the diluent to one another. Furthermore, the performance of the determined optimal solvent (10 mM CyMe 4-BTBP in 30% v/v TBP and 70% v/v FS-13) on various simulated PUREX raffinate solutions was tested. It was found that the solvent extracts all transuranic elements with high efficiency and good selectivity with regard to most other elements (fission products/activation products) present in the simulated PUREX raffinate solutions. Moreover, the solvent was found to extract a significant amount of acid. Palladium, silver, and cadmium were co-extracted along with the TRUradionuclides, which has also been observed in other similar CHALMEX systems. The extraction of plutonium and uranium was preserved for all tested simulated PUREX raffinate solutions compared to experiments using trace amounts.

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