Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes

Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes

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 (ZrO<sub>2</sub>) with magnesia (MgO) to form ultrafine-grained ZrO<sub>2</sub>–MgO composite ceramics. On the...

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Main Authors: Wenjing Qin, Mengqing Hong, Yongqiang Wang, Jun Tang, Guangxu Cai, Ran Yin, Xuefeng Ruan, Bing Yang, Changzhong Jiang, Feng Ren
Format: Article
Language:English
Published: MDPI AG 2019-08-01
Series:Materials
Subjects:
ZrO<sub>2</sub>–MgO
ultrafine grain
irradiation
He bubble
phase transformation
Online Access:https://www.mdpi.com/1996-1944/12/17/2649
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spelling doaj-1b646f7ac96440d48855a87fc0581f9c2020-11-25T02:20:27ZengMDPI AGMaterials1996-19442019-08-011217264910.3390/ma12172649ma12172649Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain SizesWenjing Qin0Mengqing Hong1Yongqiang Wang2Jun Tang3Guangxu Cai4Ran Yin5Xuefeng Ruan6Bing Yang7Changzhong Jiang8Feng Ren9School 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 430072, ChinaSchool 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 430072, ChinaMaterials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545, USASchool 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 430072, ChinaSchool 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 430072, ChinaSchool 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 430072, ChinaSchool of Power and Mechanical Engineering, Wuhan University, Wuhan 430072, ChinaSchool of Power and Mechanical Engineering, Wuhan University, Wuhan 430072, ChinaSchool 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 430072, ChinaSchool 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 430072, ChinaDeveloping high-radiation-tolerant inert matrix fuel (IMF) with a long lifetime is important for advanced fission nuclear systems. In this work, we combined zirconia (ZrO<sub>2</sub>) with magnesia (MgO) to form ultrafine-grained ZrO<sub>2</sub>–MgO composite ceramics. On the one hand, the formation of phase interfaces can stabilize the structure of ZrO<sub>2</sub> 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 ZrO<sub>2</sub> (YSZ) and MgO. Regarding He<sup>+</sup> ion irradiation with low displacement damage, the ZrO<sub>2</sub>–MgO composite ceramic with smaller grain size had a better ability to manage He bubbles than the composite ceramic with larger grain size. However, the ZrO<sub>2</sub>–MgO 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.https://www.mdpi.com/1996-1944/12/17/2649ZrO<sub>2</sub>–MgOultrafine grainirradiationHe bubblephase transformation
collection DOAJ
language English
format Article
sources DOAJ
author Wenjing Qin
Mengqing Hong
Yongqiang Wang
Jun Tang
Guangxu Cai
Ran Yin
Xuefeng Ruan
Bing Yang
Changzhong Jiang
Feng Ren
spellingShingle Wenjing Qin
Mengqing Hong
Yongqiang Wang
Jun Tang
Guangxu Cai
Ran Yin
Xuefeng Ruan
Bing Yang
Changzhong Jiang
Feng Ren
Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes
Materials
ZrO<sub>2</sub>–MgO
ultrafine grain
irradiation
He bubble
phase transformation
author_facet Wenjing Qin
Mengqing Hong
Yongqiang Wang
Jun Tang
Guangxu Cai
Ran Yin
Xuefeng Ruan
Bing Yang
Changzhong Jiang
Feng Ren
author_sort Wenjing Qin
title Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes
title_short Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes
title_full Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes
title_fullStr Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes
title_full_unstemmed Different Radiation Tolerances of Ultrafine-Grained Zirconia–Magnesia Composite Ceramics with Different Grain Sizes
title_sort different radiation tolerances of ultrafine-grained zirconia–magnesia composite ceramics with different grain sizes
publisher MDPI AG
series Materials
issn 1996-1944
publishDate 2019-08-01
description 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 (ZrO<sub>2</sub>) with magnesia (MgO) to form ultrafine-grained ZrO<sub>2</sub>–MgO composite ceramics. On the one hand, the formation of phase interfaces can stabilize the structure of ZrO<sub>2</sub> 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 ZrO<sub>2</sub> (YSZ) and MgO. Regarding He<sup>+</sup> ion irradiation with low displacement damage, the ZrO<sub>2</sub>–MgO composite ceramic with smaller grain size had a better ability to manage He bubbles than the composite ceramic with larger grain size. However, the ZrO<sub>2</sub>–MgO 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.
topic ZrO<sub>2</sub>–MgO
ultrafine grain
irradiation
He bubble
phase transformation
url https://www.mdpi.com/1996-1944/12/17/2649
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