Using in situ UO2 bicrystal sintering to understand grain boundary dislocation nucleation kinetics and creep

被引:2
作者
Dillon, Shen J. [1 ]
Finkeldei, Sarah C. [1 ,2 ,3 ]
Lang, Eric [4 ]
Hattar, Khalid [5 ]
Nelson, Andrew T. [6 ]
机构
[1] Univ Calif Irvine, Dept Mat Sci & Engn, Irvine, CA 92697 USA
[2] Univ Calif Irvine, Dept Chem, Irvine, CA USA
[3] Univ Calif Irvine, Dept Chem & Biomol Engn, Irvine, CA USA
[4] Univ New Mexico, Dept Nucl Engn, Albuquerque, NM USA
[5] Univ Tennessee, Dept Nucl Engn, Knoxville, TN USA
[6] Oak Ridge Natl Lab, Oak Ridge, TN USA
关键词
creep; grain boundaries; sinter/sintering; uranium/uranium compounds; 001 TWIST BOUNDARIES; URANIUM-DIOXIDE; ELECTRON-MICROSCOPE; DIFFUSIONAL CREEP; RADIATION-DAMAGE; COBLE CREEP; SURFACE; GROWTH; CERAMICS; ZIRCONIA;
D O I
10.1111/jace.19960
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Capillary evolution at bicrystal UO2 grain boundaries is characterized using in situ transmission electron microscopy. The discontinuous nature of the densification process, both particle rotation and axial strain, along with the large activation stress for densification support a hypothesis that grain boundary strain in UO2 follows nucleation rate limited kinetics at low to intermediate stresses, that is, less than approximate to 10(8 )Pa. The temperature dependence of the average activation stress for sintering agrees well with analysis of bulk sintering data and creep data reported within the literature when analyzed in the context of a grain boundary dislocation nucleation rate limited kinetic model.
引用
收藏
页码:6701 / 6714
页数:14
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