Accepted author manuscript, 1.02 MB, PDF document
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Accepted author manuscript, 589 KB, PDF document
Available under license: CC BY: Creative Commons Attribution 4.0 International License
Final published version
Licence: CC BY: Creative Commons Attribution 4.0 International License
Research output: Contribution to Journal/Magazine › Journal article › peer-review
Research output: Contribution to Journal/Magazine › Journal article › peer-review
}
TY - JOUR
T1 - Simulation of Neptunium Extraction in an Advanced PUREX Process — Model Improvement
AU - Chen, Hongyan
AU - Taylor, Robin J.
AU - Jobson, Megan
AU - Woodhead, David
AU - Boxall, Colin
AU - Masters, Andrew
AU - Edwards, Scott
PY - 2017
Y1 - 2017
N2 - 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 high neptunium radiolysis could help to achieve high recoveries using this flowsheet.
AB - 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 high neptunium radiolysis could help to achieve high recoveries using this flowsheet.
KW - NEPTUNIUM
KW - advanced Purex
KW - flowsheet simulation
KW - radiolysis
KW - nitrous acid
U2 - 10.1080/07366299.2016.1273684
DO - 10.1080/07366299.2016.1273684
M3 - Journal article
VL - 35
SP - 1
EP - 18
JO - Solvent Extraction and Ion Exchange
JF - Solvent Extraction and Ion Exchange
SN - 0736-6299
IS - 1
ER -