The use of 1,1,1,2,2,3,4,5,5,5-decafluoropentane (HFC-43-10mee) and tri-n-butyl phosphate (TBP) for nuclear fuel reprocessing was investigated. The extraction solvent mixtures were prepared with TBP as the extracting agent and HFC-43-10mee, n-dodecane, or a mixture of the two as the diluent. The dependence of distribution coefficient (KD) on HNO3 concentration was calculated by using a mixture of 30 vol% TBP and 70 vol% diluent and a 0.01 mol dm-3 aqueous solution of UO2(NO3) 2 and HNO3 concentration was varied from 0.3 to 4.0 mol dm-3. The uranium concentration in the aqueous phase was determined by inductively coupled plasma atomic emission spectroscopy. The results showed that the HFC-43-10mee-n-dodecane mixture was separated into two phases at low TBP concentrations, which indicated that HFC-43-10mee and n-dodecane were not miscible.
- Co-60 γ-ray irradiation
- Distribution of uranyl nitrate
- Nonflammable extraction solvent
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering