Solvent wash studies for the removal of di-butyl phosphate from spent solvent under simulated PUREX condition

Reprocessing of high plutonium content spent nuclear fuel from fast reactors results in the generation of lean organic solution containing considerably high amount of di-butyl phosphoric acid. Use of sodium carbonate as wash reagent has constraints in the view point of process operation. In this con...

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Bibliographic Details
Published in:Journal of radioanalytical and nuclear chemistry 2023-02, Vol.332 (2), p.343-353
Main Authors: Mishra, Satyabrata, Anand, P. Vishnu, Patra, Chayan, Sinha, Pranay Kumar, Mukhopadhyay, Chandan, Ravi, Jammu, Sivakumar, D., Desigan, N., Rajesh, Puspalata, Rajeev, R., Dhamodharan, K., Velavendan, P., Venkatesan, K. A., Ananthasivan, K.
Format: Article
Language:English
Subjects:
Carbonates
Chemical tests and reagents
Chemistry
Chemistry and Materials Science
Diagnostic Radiology
Dodecane
Fast nuclear reactors
Hadrons
Heavy Ions
Hydrazines
Inorganic Chemistry
Nuclear Chemistry
Nuclear energy
Nuclear industry
Nuclear Physics
Nuclear reactors
Phosphates
Phosphoric acid
Physical Chemistry
Plutonium
Radiolysis
Reagents
Reprocessing
Sodium carbonate
Solvents
Spent nuclear fuels
Spent reactor fuels
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Summary:Reprocessing of high plutonium content spent nuclear fuel from fast reactors results in the generation of lean organic solution containing considerably high amount of di-butyl phosphoric acid. Use of sodium carbonate as wash reagent has constraints in the view point of process operation. In this context, an alternative method for the wash of radiolytically degraded 1.1 M TBP/ n -dodecane was proposed. Studies indicated that that the use of 1.5 M of hydrazine carbonate was effective for the treatment of solvent degraded up to 300 kGy and the product obtained were comparable to the fresh solvent.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-022-08729-9