Energetics of metastudtite and implications for nuclear waste alteration

被引:60
作者
Guo, Xiaofeng [1 ,2 ,3 ]
Ushakov, Sergey V. [1 ,2 ]
Labs, Sabrina [4 ]
Curtius, Hildegard [4 ]
Bosbach, Dirk [4 ]
Navrotsky, Alexandra [1 ,2 ]
机构
[1] Univ Calif Davis, Peter A Rock Thermochemistry Lab, Davis, CA 95616 USA
[2] Univ Calif Davis, Nanomat Environm Agr & Technol Organized Res Unit, Davis, CA 95616 USA
[3] Univ Calif Davis, Dept Chem, Davis, CA 95616 USA
[4] Forschungszentrum Julich, Nucl Waste Management, Inst Energy & Climate Res IEK 6, D-52425 Julich, Germany
关键词
uranium; metastudtite; enthalpy of formation; stability; nuclear fuel alteration; THERMAL-DECOMPOSITION; URANIUM PEROXIDE; STUDTITE; TEMPERATURE; FUEL; CALORIMETRY; DIRECTIONS; ENTHALPIES; STABILITY; CORROSION;
D O I
10.1073/pnas.1421144111
中图分类号
O [数理科学和化学]; P [天文学、地球科学]; Q [生物科学]; N [自然科学总论];
学科分类号
07 ; 0710 ; 09 ;
摘要
Metastudtite, (UO2)O-2(H2O)(2), is one of two known natural peroxide minerals, but little is established about its thermodynamic stability. In this work, its standard enthalpy of formation, -1,779.6 +/- 1.9 kJ/mol, was obtained by high temperature oxide melt drop solution calorimetry. Decomposition of syntheticmetastudtitewas characterized by thermogravimetry and differential scanning calorimetry (DSC) with ex situ X-ray diffraction analysis. Four decomposition steps were observed in oxygen atmosphere: water loss around 220 degrees C associated with an endothermic heat effect accompanied by amorphization; another water loss from 400 degrees C to 530 degrees C; oxygen loss from amorphous UO3 to crystallize orthorhombic alpha-UO2.9; and reduction to crystalline U3O8. This detailed characterization allowed calculation of formation enthalpy from heat effects on decomposition measured by DSC and by transposed temperature drop calorimetry, and both these values agree with that from drop solution calorimetry. The data explain the irreversible transformation from studtite to metastudtite, the conditions under which metastudtite may form, and its significant role in the oxidation, corrosion, and dissolution of nuclear fuel in contact with water.
引用
收藏
页码:17737 / 17742
页数:6
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