Segregation of xenon to dislocations and grain boundaries in uranium dioxide

被引:47
|
作者
Nerikar, P. V. [1 ]
Parfitt, D. C. [2 ]
Trujillo, L. A. Casillas [1 ]
Andersson, D. A. [1 ]
Unal, C. [1 ]
Sinnott, S. B. [3 ]
Grimes, R. W. [2 ]
Uberuaga, B. P. [1 ]
Stanek, C. R. [1 ]
机构
[1] Los Alamos Natl Lab, Los Alamos, NM 87545 USA
[2] Univ London Imperial Coll Sci Technol & Med, Dept Mat, London SW7 2AZ, England
[3] Univ Florida, Dept Mat Sci & Engn, Gainesville, FL 32611 USA
来源
PHYSICAL REVIEW B | 2011年 / 84卷 / 17期
基金
英国工程与自然科学研究理事会;
关键词
ATOMIC-SCALE STRUCTURE; MOLECULAR-DYNAMICS; MICROSTRUCTURAL EVOLUTION; CERAMIC/METAL INTERFACES; RADIATION-DAMAGE; GAS-RELEASE; MGO/CU AG; UO2; CHEMISTRY; DEFECTS;
D O I
10.1103/PhysRevB.84.174105
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
It is well known that Xe, being insoluble in UO(2), segregates to dislocations and grain boundaries (GBs), where bubbles may form resulting in fuel swelling. Less well known is how sensitive this segregation is to the structure of the dislocation or GB. In this work we employ pair potential calculations to examine Xe segregation to dislocations (edge and screw) and several representative grain boundaries (Sigma 5 tilt, Sigma 5 twist, and random). Our calculations predict that the segregation trend depends significantly on the type of dislocation or GB. In particular we find that Xe prefers to segregate strongly to the random boundary as compared to the other two boundaries and to the screw dislocation rather than the edge. Furthermore, we observe that neither the volumetric strain nor the electrostatic potential of a site can be used to predict its segregation characteristics. These differences in segregation characteristics are expected to have important consequences for the retention and release of Xe in nuclear fuels. Finally, our results offer general insights into how atomic structure of extended defects influence species segregation.
引用
收藏
页数:11
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