Abstract
The mechanism of dissolution of sintered UO2 fuel pellets in nitric acid is the essential starting input information required for the design of a continuous dissolution system for spent nuclear fuel reprocessing. The current article establishes the mechanism of this reaction under typical PUREX process conditions based on the concentration profiles of nitric & nitrous acids and NO X gas composition during the course of dissolution of sintered UO2 pellets in nitric acid. The results would be useful in optimizing the dissolution process and improving the throughput of the dissolution system.
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Acknowledgements
This work forms a part of the PhD thesis of Desigan who acknowledges HNBI for giving him an opportunity to pursue his research work. He also acknowledges the support given by the management of IGCAR in carrying out the experimental work pertaining to this research project.
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Desigan, N., Bhatt, N.P., Pandey, N.K. et al. Mechanism of dissolution of nuclear fuel in nitric acid relevant to nuclear fuel reprocessing. J Radioanal Nucl Chem 312, 141–149 (2017). https://doi.org/10.1007/s10967-017-5208-z
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DOI: https://doi.org/10.1007/s10967-017-5208-z