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Development of a reconversion method for uranyl nitrate to oxide in the reconversion step of reprocessing of irradiated fuel

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Abstract

Ammonium uranyl carbonate (AUC) precipitation is developed for the conversion of uranyl nitrate to oxide in the uranium reconversion step of reprocessing of irradiated fuel by the addition of ammonium carbonate salt. Different precipitation conditions of AUC are studied. The solubility of AUC as a function of uranium concentration in the feed at different temperatures using ammonium carbonate salt as precipitant is studied. This study indicates that 95-99.8% of uranium is recovered as AUC by precipitating 5-125 g/l of uranium with loss of uranium (250-10 ppm) in the filtrate by adding ammonium carbonate salt. It is also observed that the solubility of AUC increased as the concentration of uranium decreased. Thermal decomposition is carried out by thermogravimetry/differential thermal analysis (TG/DTA) and evolved gas analysis-mass spectrometry (EGA-MS) to find out AUC decomposition and gases evolved during decomposition. Studies are also carried out to characterize AUC by using X-ray diffraction (XRD). The data show that AUC obtained by the above conditions is very much consistent with published information.

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Authors and Affiliations

  1. Reprocessing Plant Operations Division, Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, 603 102, India

    P. Govindan, A. Palamalai, K. S. Vijayan, S. Subbuthai, S. Murugesan, S. V. Mohan & R. V. Subba Rao

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  1. P. Govindan
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  2. A. Palamalai
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  3. K. S. Vijayan
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  4. S. Subbuthai
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  5. S. Murugesan
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  6. S. V. Mohan
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  7. R. V. Subba Rao
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Govindan, P., Palamalai, A., Vijayan, K.S. et al. Development of a reconversion method for uranyl nitrate to oxide in the reconversion step of reprocessing of irradiated fuel. Journal of Radioanalytical and Nuclear Chemistry 254, 65–70 (2002). https://doi.org/10.1023/A:1020837430070

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