Simulation of Neptunium Extraction in an Advanced PUREX Process — Model Improvement

Research output: Contribution to journalArticle

  • External authors:
  • Hongyan Chen
  • Robin J. Taylor
  • David Woodhead
  • Boxall Colin
  • Scott Edwards


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.

Bibliographical metadata

Original languageEnglish
Pages (from-to)1-18
Number of pages18
JournalSolvent Extraction and Ion Exchange
Issue number1
Early online date20 Jan 2017
StatePublished - 2017

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