The tri-n-butyl phosphate-nitric acid (TBP-HNO 3 ) complex prepared by contacting the pure TBP with the concentrated HNO 3 can be used for direct dissolution of lanthanide and actinide oxides in the supercritical fluid carbon dioxide (SCF-CO 2 ). Properties of the TBP-HNO 3 complex have been studied. Experimental results showed that when the initial HNO 3 /TBP volume ratio was varied from 1∶7 to 5∶1, the concentration of HNO 3 in the TBP-HNO 3 complex changed from 1.95 to 5.89 mol/L, the [HNO 3 ]/[TBP] ratio of the TBP-HNO 3 complex changed from 0.61 to 2.22, and the content of H 2 O in the TBP-HNO 3 complex changed from 2.02% to 4.19%. All of the density, viscosity and surface tension of the TBP-HNO 3 complex changed with the concentration of HNO 3 in the complex, and were higher than those of the pure TBP. The protons of HNO 3 and H 2 O in the complex underwent rapid exchange to exhibit a singlet resonance peak in nuclear magnetic resonance spectra. When the TBP-HNO 3 complex was dissolved in a low dielectric constant solvent, small droplets of HNO 3 were formed that can be detected by NMR.Keywords TBP-HNO 3 complex, supercritical fluid carbon dioxide, property
IntroductionReprocessing of the spent nuclear fuel for extraction of plutonium (Pu) and uranium (U) is conventionally carried out by the PUREX process, which involves the dissolution of the spent nuclear fuel in nitric acid followed by solvent extraction of U and Pu from the acidic solution using tri-n-butyl phosphate (TBP) as extractant in kerosene dilutent.1 However, a large amount of high-level liquid radioactive wastes is produced in the PUREX process, and the cost for liquid waste treating is high.Recently, the TBP-HNO 3 complex has been found to be effective for dissolution of solid UO 2 and U 3 O 8 as well as lanthanide oxides in supercritical fluid carbon dioxide (SCF-CO 2 ).2-5 The U(IV) in solid UO 2 is possibly oxidized to U(VI) by HNO 3 in the TBP-HNO 3 complex and dissolves in SCF-CO 2 as UO 2 (NO 3 ) 2 •2TBP. The metallic nitrate complex with TBP is finally recovered by depressurizing to atmospheric pressure. The process does not involve any aqueous solution to dissolve the uranium oxides and leads to minimum generation of the wastes, therefore, it is an attractive process for the spent nuclear fuel reprocessing and decontamination of uranium-contaminated solid waste.6 A super-DIREX (supercritical fluid direct extraction) process has been suggested by Japanese scientists for direct dissolution of actinide and lanthanide oxides and extraction of these elements with SCF-CO 2 containing the TBP-HNO 3 complex.
7A remarkable increase of the dissolution rate with increase of both HNO 3 /TBP molar ratio and the content of H 2 O in the TBP-HNO 3 complex was reported for direct dissolution of uranium oxides in SCF-CO 2 .2 The physical properties of the TBP-HNO 3 complex such as density, viscosity and surface tension are important for the direct dissolution of lanthanide and actinide oxides in SCF-CO 2 . In order to understand the nature and mechani...