The separation of neptunium and technetium in an advanced PUREX process
Journal Article
·
· Solvent Extraction and Ion Exchange
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
An advanced PUREX process has been developed which can reduce TRU waste volume and the environmental hazard risk due to long-lived nuclides. The separation of neptunium and technetium from plutonium and uranium solutions has been studied before the U/Pu partitioning step in the PUREX process. The effectiveness of normal-butyraldehyde as a reductant of Np(VI) to Np(V) and of high acid scrubbing of technetium was shown in a basic study and a chemical flowsheet study.
- Sponsoring Organization:
- USDOE
- OSTI ID:
- 346977
- Journal Information:
- Solvent Extraction and Ion Exchange, Journal Name: Solvent Extraction and Ion Exchange Journal Issue: 5 Vol. 16; ISSN 0736-6299; ISSN SEIEDB
- Country of Publication:
- United States
- Language:
- English
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