Dissolution of Actinide Oxides in Carbonate Solutions

被引：0
|
作者：
Chervyakov, N. M. [1 ,2 ]
Boyarintsev, A. V. [1 ,2 ]
Kostikova, G. V. [3 ]
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
[3] Russian Acad Sci, Frumkin Inst Phys Chem & Electrochem, Moscow 119071, Russia
来源：
RADIOCHEMISTRY | 2023年 / 65卷 / 03期
基金：
俄罗斯科学基金会;
关键词：
uranium dioxide; triuranium octoxide; plutonium dioxide; neptunium dioxide; oxidative dissolution; carbonate media; hydrogen peroxide; persulfate; SPENT NUCLEAR-FUEL; HYDROGEN-PEROXIDE; URANIUM; PRECIPITATION; RECOVERY;
D O I：
10.1134/S1066362223030025
中图分类号：
O65 [分析化学];
学科分类号：
070302 ; 081704 ;
摘要：
The dissolution step of uranium and mixed oxide uranium-plutonium spent nuclear fuel is a key initial step of a new alternative hydrometallurgical method-the CARBEX process. The study considers carbonate oxidizing systems NaHCO3/Na2CO3-H2O2/2Na(2)CO(3)& BULL;3H(2)O(2)/\M2S2O8, where M = Na, K, or NH4+, for dissolving actinide oxide powders. The chemical and physical factors that determine the rate of oxidative dissolution of powdered individual oxides UO2, U3O8, PuO2 and NpO2 in carbonate media were found. The results obtained are important for the development of the oxidative and sonochemical options of dissolution of highly calcined crystalline samples of uranium, plutonium and neptunium oxides, as well of spent nuclear fuel in carbonate media.
引用
收藏
页码：276 / 287
页数：12
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