Technology for reprocessing mother liquor and washing solution from crystalization purification of HTGR SNF

Author:

Tkachenko L. I.1,Vidanov V. L.2,Kenf E. V.1,Volodina N. Yu.1,Pleshakov Ya. O.1,Shadrin A. Yu.3

Affiliation:

1. Khlopin Radium Institute

2. Bochvar High-Technology Research Institute of Inorganic Materials

3. Science and Innovations Private Enterprise for Nuclear Industry Scientific Development

Abstract

The extractants diphenyl-N,N-dioctylcarbamoylmethylphosphine oxide and diphenyl-N,N-diisobutylcarbamoylmethylphosphine oxide for the processing of spent fuel were tested. The conditions for extraction and separation of uranium and TPE–REE were determined. A technological scheme was proposed for processing spent nuclear fuel from high-temperature gas-cooled reactors. During dynamic testing, at least 99.9% of uranium and plutonium and at least 99.5% of americium and rare earth elements were extracted. The TPE + REE and U+Pu fractions were isolated. The U+Pu fraction contained approximately 5% Am, while the TPE + REE fraction had less than 0.1% U and Pu.

Publisher

The Russian Academy of Sciences

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