Effects of He Irradiation on Yttria‐Stabilized Zirconia Ceramics

Journal of the American Ceramic Society - Tập 98 Số 4 - Trang 1314-1322 - 2015
Tengfei Yang1, Caitlin A. Taylor2, Chenxu Wang1, Yanwen Zhang2,3, William J. Weber2,3, Jingren Xiao1, Jianming Xue1, Sha Yan1, Yugang Wang1
1State Key Laboratory of Nuclear Physics and Technology, Center for Applied Physics and Technology, Peking University, Beijing 100871, China
2Department of Materials Science and Engineering, University of Tennessee, Knoxville, Tennessee 37996
3Materials Science & Technology Division Oak Ridge National Laboratory Oak Ridge Tennessee 37831‐6138

Tóm tắt

Effects of He irradiation on polycrystalline yttria‐stabilized zirconia (YSZ) are studied with the focus on irradiation‐induced damage buildup, He behavior, and volume swelling. The evolution of irradiation‐induced structural damage in polycrystalline YSZ, which is independent of grain orientation, is described by a multistep damage accumulation model. A three‐step damage evolution process was found, and different types of defects were observed in the different damage steps. Compared with single‐crystal YSZ, the second damage step occurs at a lower dose in polycrystalline YSZ due to the initial defects and strain. The implanted He ions are readily trapped along the grain boundaries and the mobility of He ions is greatly increased. The enhanced He mobility along the grain boundary leads to a lower threshold irradiation dose and a larger penetration depth for bubble formation. Similar morphologies are observed for the He bubbles in the polycrystalline YSZ and in single‐crystal YSZ, and the formation of He bubbles in polycrystalline YSZ is not influenced by grain orientation. As both the extended defects and He bubbles can induce volume swelling, the variation in volume swelling as a function of dose can be divided into a two stage process.

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Thông tin xuất bản

Journal of the American Ceramic Society

Tập 98 Số 4

1314-1322

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