Actinide extraction from simulated and irradiated spent nuclear fuel using TBP solutions in HFC-134a
Conference
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OSTI ID:21230375
- Khlopin Radium Institute, RPA, 28, 2-nd Murinskii ay., St-Petersburg (Russian Federation)
It was demonstrated that solutions of TBP-nitric acid adduct in liquid Freon HFC-134a (1.2 MPa, 25 deg. C) allowed for recovery of uranium with nearly the same effectiveness as supercritical CO{sub 2} at 30 MPa. At nearly quantitative recovery of U and Pu, a DF of ca. 10 can be attained on dissolution and extraction of simulated SNF samples. The possibility of recovery of actinides contained in cakes produced by oxide conversion of simulated and irradiated SNF with solutions of TBP and DBE in Freon HFC-134a was shown. (authors)
- Research Organization:
- Chemical Sciences Division, Oak Ridge National Laboratory (United States)
- OSTI ID:
- 21230375
- Resource Relation:
- Conference: ISEC 2008: International Solvent Extraction Conference on Solvent Extraction: Fundamentals to Industrial Applications, Tucson, AZ (United States), 15-19 Sep 2008; Other Information: Country of input: France; 13 refs; Related Information: In: Proceedings of ISEC 2008, International Solvent Extraction Conference - Solvent Extraction: Fundamentals to Industrial Applications, by Moyer, Bruce A. (ed.), 1740 pages.
- Country of Publication:
- United States
- Language:
- English
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