Dissolution Study of Thorium-Uranium Oxides in Aqueous Triflic Acid Solutions

被引:4
|
作者
Bulemela, E. [1 ]
Bergeron, A. [1 ]
Stoddard, T. [1 ]
机构
[1] Canadian Nucl Labs, 286 Plant Rd, Chalk River, ON K0J 1J0, Canada
来源
ATALANTE 2016 INTERNATIONAL CONFERENCE ON NUCLEAR CHEMISTRY FOR SUSTAINABLE FUEL CYCLES | 2016年 / 21卷
关键词
Dissolution kinetics; Triflic acid; Thorium-Uranium oxides; Nuclear fuel; Sintered mixed oxides; TRIFLUOROMETHANESULFONATE;
D O I
10.1016/j.proche.2016.10.034
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
(T)he dissolution of sintered mixed oxides of thorium with uranium in various concentrations of trifluoromethanesulfonic (triflic) acid solutions was investigated under reflux conditions to evaluate the suitability of the method. Various fragment sizes (1.00 mm < x < 7.30 mm) of sintered (Th,U)O-2 and simulated high-burnup nuclear fuel (SIMFUEL) were almost completely dissolved in a few hours, which implies that triflic acid could be used as an alternative to the common dissolution method, involving nitric acid-hydrofluoric acid mixture. The influence of acid concentration, composition of the solids, and reaction time on the dissolution yield of Th and U ions was studied using Inductively Coupled Plasma-Mass Spectrometry (ICP-MS). The dissolution rate was found to depend upon the triflic acid concentration and size of the solid fragments, with near complete dissolution for the smallest fragments occurring in boiling 87% w/w triflic acid. The formation of Th and U ions in solution appears to occur at the same rate as the triflic acid simultaneously reacts with the constituent oxides as evidenced by the results of a constant U/Th concentration ratio with the progress of the dissolution. Crown Copyright (C) 2016 Published by Elsevier B.V.
引用
收藏
页码:239 / 246
页数:8
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