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用于包层的xLiZrO-(1-x)MgO陶瓷材料的合成、结构与强度性能

Synthesis and Structural and Strength Properties of xLiZrO-(1-x)MgO Ceramics-Materials for Blankets.

作者信息

Shlimas Dmitriy I, Borgekov Daryn B, Kozlovskiy Artem L, Zdorovets Maxim V

机构信息

Laboratory of Solid State Physics, The Institute of Nuclear Physics, Almaty 050032, Kazakhstan.

Engineering Profile Laboratory, L.N. Gumilyov Eurasian National University, Astana 010008, Kazakhstan.

出版信息

Materials (Basel). 2023 Jul 23;16(14):5176. doi: 10.3390/ma16145176.

DOI:10.3390/ma16145176
PMID:37512449
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC10385392/
Abstract

The article considers the effect of doping with magnesium oxide (MgO) on changes in the properties of lithium-containing ceramics based on lithium metazirconate (LiZrO). There is interest in this type of ceramics on account of their prospects for application in tritium production in thermonuclear power engineering, as well as several other applications related to alternative energy sources. During the investigations undertaken, it was found that variation in the MgO dopant concentration above 0.10-0.15 mol resulted in the formation of impurity inclusions in the ceramic structure in the form of a MgLiZrO phase, the presence of which resulted in a rise in the density of the ceramics, along with elevation in resistance to external influences. Moreover, during experimental work on the study of the thermal stability of the ceramics to external influences, it was found that the formation of two-phase ceramics resulted in growth in the preservation of stable strength properties during high-temperature cyclic tests. The decrease in strength characteristics was observed to be less than 1%.

摘要

本文探讨了用氧化镁(MgO)掺杂对基于偏锆酸锂(LiZrO)的含锂陶瓷性能变化的影响。由于这类陶瓷在热核聚变工程中生产氚的应用前景,以及与替代能源相关的其他一些应用,人们对其产生了兴趣。在进行的研究中发现,当MgO掺杂剂浓度变化超过0.10 - 0.15摩尔时,会在陶瓷结构中形成MgLiZrO相形式的杂质夹杂物,其存在导致陶瓷密度增加,同时对外界影响的抗性提高。此外,在研究陶瓷对外部影响的热稳定性的实验工作中发现,两相陶瓷的形成导致在高温循环测试期间稳定强度性能的保留增加。观察到强度特性的下降小于1%。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/2b737173ca03/materials-16-05176-g010.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/f46512549145/materials-16-05176-g001a.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/94f6c8247d2e/materials-16-05176-g002.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/640d4da4320e/materials-16-05176-g003.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/8fa4f74ecade/materials-16-05176-g004.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/57920f4f2f12/materials-16-05176-g005.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/8b46918f6759/materials-16-05176-g006.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/69da258ef998/materials-16-05176-g007.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/5d377aae97f1/materials-16-05176-g008.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/316545a9abc0/materials-16-05176-g009.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/2b737173ca03/materials-16-05176-g010.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/f46512549145/materials-16-05176-g001a.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/94f6c8247d2e/materials-16-05176-g002.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/640d4da4320e/materials-16-05176-g003.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/8fa4f74ecade/materials-16-05176-g004.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/57920f4f2f12/materials-16-05176-g005.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/8b46918f6759/materials-16-05176-g006.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/69da258ef998/materials-16-05176-g007.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/5d377aae97f1/materials-16-05176-g008.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/316545a9abc0/materials-16-05176-g009.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/61b4/10385392/2b737173ca03/materials-16-05176-g010.jpg

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本文引用的文献

1
Study of Structural and Strength Changes in Lithium-Containing Ceramics-Potential Blanket Materials for Nuclear Power, Subjected to High-Dose Proton Irradiation.含锂陶瓷(核电潜在包层材料)在高剂量质子辐照下的结构与强度变化研究
Materials (Basel). 2022 Aug 13;15(16):5572. doi: 10.3390/ma15165572.
2
Ultrafast Carbon Dioxide Sorption Kinetics Using Morphology-Controllable Lithium Zirconate.使用形态可控的锆酸锂的超快二氧化碳吸附动力学
ACS Appl Mater Interfaces. 2019 Jan 9;11(1):691-698. doi: 10.1021/acsami.8b16463. Epub 2018 Dec 26.