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Effect of H2O2, NaClO and Fe on the dissolution of unirradiated UO2in NaCl 5 mol kg−1. Comparison with spent fuel dissolution experiments

Authors
Journal
Journal of Nuclear Materials
0022-3115
Publisher
Elsevier
Publication Date
Volume
238
Issue
1
Identifiers
DOI: 10.1016/s0022-3115(96)00341-8
Keywords
  • Section 3. Studies On Simulated Fuel And Uranium Dioxide

Abstract

Abstract The effect of H 2O 2, NaClO and Fe on the dissolution of unirradiated UO 2(s) in NaCl 5 mol kg −1 has been studied at neutral to alkaline pH. Dissolution rates have been determined as a function of oxidant concentration. A general equation to correlate both parameters has been obtained: log r = (− 8.0 ± 0.2) + log[ Ox] 0.93 ± 0.07. The values obtained have been compared to those given for spent fuel under the same experimental conditions. The effect of iron is similar in both unirradiated UO 2 and spent fuel with a final uranium concentration around 5 × 10 −8 mol kg −1 which corresponds to the solubility value of UO 2(f) under reducing conditions.

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