Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes
- School of Physics and Technology, Center for Ion Beam Application, Hubei Nuclear Solid Physics Key Laboratory and MOE Key Laboratory of Artificial Micro- and Nano-Structures, Wuhan University, Wuhan, China; School of Physics and Electronics, Key Laboratory of Low Dimensional Quantum Structures and Quantum Control, Hunan Normal University, Changsha, China
- School of Physics and Technology, Center for Ion Beam Application, Hubei Nuclear Solid Physics Key Laboratory and MOE Key Laboratory of Artificial Micro- and Nano-Structures, Wuhan University, Wuhan, China; The Institute of Technological Sciences, Wuhan University, Wuhan, China
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Materials Science and Technology Div.
- School of Physics and Technology, Center for Ion Beam Application, Hubei Nuclear Solid Physics Key Laboratory and MOE Key Laboratory of Artificial Micro- and Nano-Structures, Wuhan University, Wuhan, China
- School of Power and Mechanical Engineering, Wuhan University, Wuhan, China
Developing high-radiation-tolerant inert matrix fuel (IMF) with a long lifetime is important for advanced fission nuclear systems. In this work, we combined zirconia (ZrO2) with magnesia (MgO) to form ultrafine-grained ZrO2–MgO composite ceramics. On the one hand, the formation of phase interfaces can stabilize the structure of ZrO2 as well as inhibiting excessive coarsening of grains. On the other hand, the grain refinement of the composite ceramics can increase the defect sinks. Two kinds of composite ceramics with different grain sizes were prepared by spark plasma sintering (SPS), and their radiation damage behaviors were evaluated by helium (He) and xenon (Xe) ion irradiation. It was found that these dual-phase composite ceramics had better radiation tolerance than the pure yttria-stabilized ZrO2 (YSZ) and MgO. Regarding He+ ion irradiation with low displacement damage, the ZrO2–Mg composite ceramic with smaller grain size had a better ability to manage He bubbles than the composite ceramic with larger grain size. However, the ZrO2–Mg composite ceramic with a larger grain size could withstand higher displacement damage in the phase transformation under heavy ion irradiation. Therefore, the balance in managing He bubbles and phase stability should be considered in choosing suitable grain sizes.
- Research Organization:
- Los Alamos National Lab (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA); National Science Fund for Excellent Young Scholars; Natural Science Foundation of China; Natural Science Foundation of Hubei Province, China; Scientific and Technological Innovation Projects; Fundamental Research Funds for the Central Universities
- Grant/Contract Number:
- AC52-06NA25396; 11522543; 11875207; 11475129; 51571153; 11935011; 11905058; 2016CFA080; 2018GK2064
- OSTI ID:
- 1628411
- Journal Information:
- Materials, Vol. 12, Issue 17; ISSN 1996-1944
- Publisher:
- MDPICopyright Statement
- Country of Publication:
- United States
- Language:
- English
Similar Records
Nanochannel structures in W enhance radiation tolerance
Bubble formation and lattice parameter changes resulting from He irradiation of defect-fluorite Gd2Zr2O7