Effect of some reducing and complexing agents on the extraction behavior of technetium in the TBP-HNO3 system

Melent’ev, A. B.; Mashkin, A. N.; Tugarina, O. V.; Kolupaev, D. N.; Zilberman, B. Ya.; Тананаев, И. Г.

doi:10.1134/s1066362211030052

Cited by 13 publications

(3 citation statements)

References 7 publications

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“…Melent'ev et al [36] considered the possibility of using hydroxyethylhydrazine as Pu(III) stabilizer instead of traditional hydrazine in the operation of reductive stripping of Pu in its separation from U in the first cycle. This problem is topical not only because of the salt-forming nature of hydrazine, but also because of the fact that hydrazine is unstable in HNO 3 solutions in the presence of Tc ions [37], and specifically its instability is the major factor responsible for disturbances of the U/Pu splitting process [38].…”

Section: Substituted Hydrazinesmentioning

confidence: 99%

“…However, hydroxyethylhydrazine reduces Tc(VII) to Tc(IV) very slowly ( Substituted hydroxylamines (SHAs) of the general formula RR'NHOH + (where R = СН 3 , C 3 H 7 ; R' = H, CH 3 , C 2 H 5 ) are considered, along with SHs, as promising agents for technology [10]. It is stated [10] 0.1 M, and 40°C) and cannot adequately replace hydrazine as stabilizer [36].…”

Section: Substituted Hydrazinesmentioning

confidence: 99%

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Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

Marchenko

Alekseenko²,

Dvoeglazov

2015

Radiochemistry

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Scientific, technical, and patent information on the use of organic compounds as reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing is summarized and correlated. Organic derivatives of hydrazine and hydroxylamine, and also oximes and urea derivatives at relatively low acidities and temperatures reduce Np(VI) to Np(V) and Pu(IV) to Pu(III). As the acidity and temperature are increased, Np(V) is slowly reduced to Np(IV). Alcohols, aldehydes, hydrocarbons, and acetic acid were identified among products of oxidation of the organic compounds in nitric acid medium. The above-named organic reductants can be used in different steps of the PUREX process: separation of Pu and Np from U in the first extraction cycle, purification of U to remove Np in the second cycle of uranium purification, and Pu stripping in the step of its final purification. Laboratory experiments performed on countercurrent extraction installations of mixersettlers and of centrifugal contactors demonstrated the possibility of reaching high separation factors of U from Pu and/or Np and high degrees of plutonium concentration to obtain Pu strips containing up to 150 g L -1 Pu.

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Section: Substituted Hydrazinesmentioning

confidence: 99%

Section: Substituted Hydrazinesmentioning

confidence: 99%

Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

Marchenko

Alekseenko²,

Dvoeglazov

2015

Radiochemistry

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“…In this work, different extractants and disperser solvents were studied. Previously reported extractants for Tc, such as tributyl phosphate (TBP) and triisooctylamine (TiOA) [7][8][9][10], were tested in different percentages in xylene and dodecane. The quaternary ammonium salt Aliquat®336, which is used as a Tc extractant in commercial resins, was also studied.…”

mentioning

confidence: 99%

Automatic in-syringe dispersive liquid–liquid microextraction of 99Tc from biological samples and hospital residues prior to liquid scintillation counting

et al. 2015

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A new approach exploiting in-syringe dispersive liquid-liquid microextraction (DLLME) for (99)Tc extraction and preconcentration from biological samples, i.e., urine and saliva, and liquid residues from treated patients is presented. (99)Tc is a beta emitter with a long half-life (2.111 × 10(5) years) and mobility in the different environmental compartments. One of the sources of this radionuclide is through the use of its father (99m)Tc in medical diagnosis. For the first time a critical comparison between extractants and disperser solvents for (99)Tc DLLME is presented, e.g., tributyl phosphate (TBP), trioctylmethylammonium chloride (Aliquat®336), triisooctylamine (TiOA), as extractants in apolar solvents such as xylene and dodecane, and disperser solvents such as acetone, acetonitrile, ethanol, methanol, 1-propanol, and 2-propanol. The system was optimized by experimental design, and 22.5% of Aliquat®336 in acetone was selected as extractant and disperser, respectively. Off-line detection was performed using a liquid scintillation counter. The present method has a (99)Tc minimum detectable activity (MDA) of 0.075 Bq with a high extraction/preconcentration frequency (8 h(-1)). Urine, saliva, and hospital residues were satisfactorily analyzed with recoveries of 82-119%. Thus, the proposed system is an automatic powerful tool to monitor the entry of (99)Tc into the environment. Graphical Abstract (99m)Tc is widely used in Nuclear Medicine for diagnosis. Its daugther (99)Tc is automatically monitored in biological samples from treated patients by in-syringe dispersive liquid-liquid microextraction.

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The coordination of low-valent Re/Tc with glutarimide dioxime and the fate of Tc in aqueous solution: spectroscopy, ESI–MS and EXAFS

Yin

et al. 2021

J Radioanal Nucl Chem

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Effect of some reducing and complexing agents on the extraction behavior of technetium in the TBP-HNO3 system

Cited by 13 publications

References 7 publications

Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

Organic reductants of Pu and Np ions in wet technology for spent nuclear fuel reprocessing

Automatic in-syringe dispersive liquid–liquid microextraction of 99Tc from biological samples and hospital residues prior to liquid scintillation counting

The coordination of low-valent Re/Tc with glutarimide dioxime and the fate of Tc in aqueous solution: spectroscopy, ESI–MS and EXAFS

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