Influence of temperature on the corrosion of uranium dioxide nuclear fuel

被引：0

作者：

Broczkowski, Michael E. ^{[1
]}

Noel, Jamic J. ^{[1
]}

Shoesmith, David W. ^{[1
]}

机构：

[1] Univ Western Ontario, Dept Chem, 1151 Richmond St, London, ON N6A 5B7, Canada

来源：

SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXX | 2007年 / 985卷

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中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The anodic dissolution Of UO2 has been studied at 60 degrees C and the results compared to previous observations at 22 degrees C. The rate of oxidation/dissolution was determined electrochemically at constant potentials in the range -500 mV to 500 mV (vs. SCE). The composition of the electrochemically oxidized surface was determined by X-Ray Photoelectron Spectroscopy (XPS). The onset of oxidation (UO2 -> UO2+x) occurred at approximately the same potential (400 mV) at both temperatures. However, the conversion of U-V to U-VI, and hence to soluble UO22+, was accelerated by temperature. This acceleration of dissolution caused the development of acidity at localized sites on the fuel surface at lower (less oxidizing) potentials (>= 100 mV) at 60 degrees C than at 22 degrees C (>= 3,50 mV).

引用

页码：59 / +

页数：3

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