TY - JOUR
T1 - Effects of He ion irradiation on the microstructures and mechanical properties of t' phase yttria-stabilized zirconia ceramics
AU - Pu, Guo
AU - Zou, Jianxiong
AU - Lin, Liwei
AU - Zhang, Kun
AU - Liu, Bo
AU - Ma, Fei
AU - Wang, Qiangbing
AU - Li, Qiran
N1 - Publisher Copyright:
© 2018 Elsevier B.V.
PY - 2019/1/15
Y1 - 2019/1/15
N2 - The dense ZrO2-8 wt.% Y2O3 ceramics with tetragonal (t') phase were prepared by spark plasma sintering (SPS). The micro-structure modification in poly-crystalline t' phase YSZ ceramics irradiated with 60 KeV He ions over a wide fluence range were studied. It is found that, the t' → t + c phase transformation was detected for the samples irradiated at the fluence above 2 × 1017 cm−2. In addition, a three-steep model for damage stages has been proposed and discussed for interpreting the evolution of mechanical properties of t'-YSZ ceramics after irradiated, mainly revealed by the analysis from HRTEM results. Firstly, as the He+ fluences range from 0.5 × 1017 cm−2 to 1 × 1017 cm−2, the hardening effects were confirmed in t'-YSZ owing to the irradiation induced defects serve as obstacles to resist slipping of dislocations. As the fluence was increased to 2 × 1017 cm−2, the degradation of mechanical properties was evidenced, which could be ascribed to the deterioration effect of aggregated He bubbles inside t' YSZ grains. While the fluence increased to 10 × 1017 cm−2, a seriously damaged region was approximately located at 250 nm in depth, at which a great number of He bubbles with different shape and dislocation loops were evidenced, leading to a further reduction of hardness and elastic modulus. No micro-cracks emerge even for He+ fluences as high as 10 × 1017 cm−2, indicating high irradiation stability and resistance to micro-crack propagation in t'-YSZ.
AB - The dense ZrO2-8 wt.% Y2O3 ceramics with tetragonal (t') phase were prepared by spark plasma sintering (SPS). The micro-structure modification in poly-crystalline t' phase YSZ ceramics irradiated with 60 KeV He ions over a wide fluence range were studied. It is found that, the t' → t + c phase transformation was detected for the samples irradiated at the fluence above 2 × 1017 cm−2. In addition, a three-steep model for damage stages has been proposed and discussed for interpreting the evolution of mechanical properties of t'-YSZ ceramics after irradiated, mainly revealed by the analysis from HRTEM results. Firstly, as the He+ fluences range from 0.5 × 1017 cm−2 to 1 × 1017 cm−2, the hardening effects were confirmed in t'-YSZ owing to the irradiation induced defects serve as obstacles to resist slipping of dislocations. As the fluence was increased to 2 × 1017 cm−2, the degradation of mechanical properties was evidenced, which could be ascribed to the deterioration effect of aggregated He bubbles inside t' YSZ grains. While the fluence increased to 10 × 1017 cm−2, a seriously damaged region was approximately located at 250 nm in depth, at which a great number of He bubbles with different shape and dislocation loops were evidenced, leading to a further reduction of hardness and elastic modulus. No micro-cracks emerge even for He+ fluences as high as 10 × 1017 cm−2, indicating high irradiation stability and resistance to micro-crack propagation in t'-YSZ.
KW - Helium ion irradiation
KW - Mechanical properties
KW - Phase transformation
KW - Spark plasma sintering
KW - Yttria-stabilized zirconia ceramic
UR - https://www.scopus.com/pages/publications/85053004501
U2 - 10.1016/j.jallcom.2018.08.259
DO - 10.1016/j.jallcom.2018.08.259
M3 - 文章
AN - SCOPUS:85053004501
SN - 0925-8388
VL - 771
SP - 777
EP - 783
JO - Journal of Alloys and Compounds
JF - Journal of Alloys and Compounds
ER -