Authors:Y. Rao, R. Yadav, R. Swamy, B. Gopalan, and S. Syamsundar
The two step oxidation of UO2+x and reduction of U3O8 powders observed during Differential Thermal Analysis (DTA) has been exploited to determine their Specific Surface Areas
(SSAs). The results obtained by this method have been compared with the Braunauer, Emmett and Teller (BET) method and are
found to be in good agreement in the SSA range of 2–4 m2/gm in the case of UO2+x obtained from ADU route and 4–8 m2/gm in the case of AUC route. A precision of ±0.1 m2/gm is obtained. The maximum temperature of oxidation and reduction of these oxides are dependent upon their preparative routes
such as Ammonium Diuranate (ADU) and Ammonium Uranyl Carbonate (AUC).
Authors:G. Krishna, H. Ravindra, B. Gopalan, and S. Syamsundar
Tri-n-butyl phosphate (TBP) continues to be the most widely used solvent in nuclear fuel extraction, refining and reprocessing units for the extraction of actinides and their separation from fission products. An X-ray fluorescence spectrometric method (XRFS) for the determination of TBP content with an X-ray detectable element is presented. The method involves formation of an ion association complex of uranium with TBP-kerosene mixture in 3M nitric acid. The analytes uranium and bromine used as internal ratio elements in organic extract are excited by a primary X-ray beam from a rhodium tube. The solvent concentration is determined from the ratioed characteristic intensities of uranium and bromine. The procedure permits the determination of organic solvent in the range 0.5 to 5.0% with a relative standard deviation of 0.1%.
Authors:B. Narasimha Murty, B. Prakash Rao, L. Lingaiah, R. Yadav, B. Gopalan, and S. Syamsunder
This paper describes a method of calculation of saturated concentration of uranium in TBP, the organic phase obtained in a solvent extraction process in a uranium extraction plant. The calculation utilizes only the other available routine parameter such as %TBP in the respective lean solvent.