Oxidative Dissolution of Uranium Dioxide and Triuranium Octoxide in Carbonate Media

被引：0
|
作者：
Chervyakov, N. M. [1 ,2 ]
Boyarintsev, A. V. [1 ,2 ]
Stepanov, S. I. [1 ,2 ]
机构：
[1] Mendeleev Univ Chem Technol Russia, Moscow 125047, Russia
[2] Natl Res Nucl Univ Moscow Engn Phys Inst, Ozersk Inst Technol, Ozersk 456783, Chelyabinsk Obl, Russia
来源：
RADIOCHEMISTRY | 2023年 / 65卷 / 02期
基金：
俄罗斯科学基金会;
关键词：
uranium dioxide; triuranium octoxide; oxidative dissolution; carbonate solutions; SPENT NUCLEAR-FUEL;
D O I：
10.1134/S1066362223020182
中图分类号：
O65 [分析化学];
学科分类号：
070302 ; 081704 ;
摘要：
Oxidative dissolution of powdered UO2 and U3O8 samples in Na2CO3/NaHCO3-H2O2 solutions was studied. The U3O8 samples were prepared from UO2 at 480-1200 degrees C. The rate and degree of the U3O8 dissolution depend on the characteristics of the oxide powder and on the dissolution temperature. The process rate constants under the conditions of the experiments were calculated. Based on the results obtained, the conditions of complete dissolution of UO2 and U3O8 in Na2CO3/NaHCO3-H2O2 solutions were determined.
引用
收藏
页码：257 / 260
页数：4
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