Technology for reprocessing mother liquor and washing solution from crystalization purification of HTGR SNF
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.
Authors
- Ya. O. Pleshakov
- E. Kenf
- A. Yu. Shadrin (ORCID: https://orcid.org/0000-0002-4042-0443)
- Л. И. Ткаченко (ORCID: https://orcid.org/0009-0000-3780-0368)
- V. L. Vidanov (ORCID: https://orcid.org/0000-0001-6182-4116)
- N. Yu. Volodina
Institutions
- V. G. Khlopin Radium Institute (RU)
- "VNIINM" named after AA Bochvar (RU)
Publication Details
- Journal
- РАДИОХИМИЯ
- Published
- 2024-09-13
- DOI
- https://doi.org/10.31857/s0033831124020067
- Citations
- 1
- Primary Topic
- Extraction and Separation Processes
- Type
- article
- Field-Weighted Citation Impact
- 0.21