Routing neptunium to a single product in spent nuclear fuel reprocessing is a significant challenge. In this work, we have further improved the simulation of neptunium extraction in an advanced PUREX flowsheet by applying a revised model of the Np(V)–Np(VI) redox reaction kinetics, a new nitric acid radiolysis model, and by evaluating various models for the nitrous acid distribution coefficient. The Np disproportionation reaction is shown to have a negligible effect. The models are validated against published ‘cold test’ experimental results; the ‘hot test’ simulation suggests that high neptunium radiolysis could help to achieve high recoveries using this flowsheet.
CITATION STYLE
Chen, H., Taylor, R. J., Jobson, M., Woodhead, D. A., Boxall, C., Masters, A. J., & Edwards, S. (2017). Simulation of Neptunium Extraction in an Advanced PUREX Process—Model Improvement. Solvent Extraction and Ion Exchange, 35(1), 1–18. https://doi.org/10.1080/07366299.2016.1273684
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