Reductive dissolution studies of CeO2 and simulated mixed oxide fuel of (Ce, U)O2 in nitric acid medium
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In dissolution studies involving plutonium oxide, oxides of cerium are employed as a non radioactive surrogate. A reductive dissolution of cerium oxide and mixed oxide consisting cerium-uranium were investigated in nitric acid medium in presence of uranous. Extensive dissolution studies were carried out using ceria powder in pure HNO3 and HNO3–[N2H5]+ [NO3]− with U(IV). The effects of temperature, mixing rate and concentration of reducing agent on dissolution efficiency of CeO2 were investigated. The apparent activation energy was calculated from Arrhenius plot for dissolution of cerium oxide in HNO3 in presence of uranous stabilized by hydrazine and it was found to be about 40 kJ mol−1 in the temperature range of 300–350 K. The fraction of total mass of uranium and cerium from the mixed oxide pellet leached as function of time was monitored during dissolution performed under optimized conditions and dissolution yield was found to be > 99%.
KeywordsReductive dissolution MOX fuel Advanced fuel Oxides of cerium Dissolution of ceria
Authors are highly thankful to Dr. A. Ravisankar, Distinguished Scientist, Director, Reprocessing Group, Dr. R. Natarajan, Former Director, Reprocessing Group and Dr. R. V. Subba Rao, Head, Process and Radio Chemistry Division for their valuable suggestions and encouragement during the course of this work. The contributions of Dr. N. Desigan during preparation of manuscript are highly acknowledged. The valuable contribution during experimental part from Shri D. Sivakumar, Shri P. K. Sharma, Shri Pugazhendi, Shri N. Srinivasan, Shri S. N. Das, Smt. Rekha and Smt. D. Jeyandhi Chemical Laboratory, Reprocessing Group is greatly acknowledged.
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Conflict of interest
The authors declare that they have no conflict of interest.
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