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Technology for Reprocessing Mother–Wash Solution after Crystallization Purification of Spent Nuclear Fuel from High Temperature Gas-Cooled Reactor.

Authors :
Tkachenko, L. I.
Vidanov, V. L.
Kenf, E. V.
Volodina, N. Yu.
Pleshakov, Ya. O.
Shadrin, A. Yu.
Source :
Radiochemistry. Apr2024, Vol. 66 Issue 2, p178-184. 7p.
Publication Year :
2024

Abstract

The extractants diphenyl-N,N-dioctylcarbamoylmethylphosphine oxide and diphenyl-N,N-diisobutylcarbamoylmethylphosphine oxide for the SNF reprocessing were tested. The conditions for extraction and separation of uranium and TPE–REE were determined. A flowsheet was proposed for reprocessing SNF from high-temperature gas-cooled reactors. Upon dynamic testing, at least 99.9% of uranium and plutonium and at least 99.5% of americium and rare earth elements were separated. The TPE + REE and U + Pu fractions were recovered. The U + Pu fraction contained approximately 5% Am, while the TPE + REE fraction had less than 0.1% U and Pu. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
10663622
Volume :
66
Issue :
2
Database :
Academic Search Index
Journal :
Radiochemistry
Publication Type :
Academic Journal
Accession number :
177280150
Full Text :
https://doi.org/10.1134/S1066362224020061