Thermal conductivity of irradiated tetragonal lithium aluminate

IF 3.3 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2025-01-15 DOI:10.1016/j.jnucmat.2024.155585

Víctor H. Ortiz , Weilin Jiang , Andrew M. Casella , David J. Senor , Ram Devanathan , S. Aria Hosseini , P. Alex Greaney , Richard B. Wilson

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Abstract

The effect of 120 keV He⁺+D⁺-ion irradiation on the thermal conductivity of ceramic tetragonal γ-LiAlO₂ is studied with time-domain thermoreflectance (TDTR) at temperatures between 300 and 700 K. The thermal conductivity of single crystal γ-LiAlO₂ is 13.5 W/(m·K) at 300 K, and scales with temperature like 1/T. The thermal conductivity of unirradiated polycrystalline γ-LiAlO₂ is 7.4 W/(m·K). Irradiation at fluences of 1 ×, 5 ×, and 10 × 10¹⁶ ions/cm² decreases the thermal conductivity by ≈ 30 %, 80 %, and 90 %. The effect of irradiation is saturated at ion fluences of 10¹⁷ ions/cm². Irradiation decreases the temperature dependence of the thermal conductivity. For ion fluences larger than 10¹⁷ ions/cm², the thermal conductivity reaches a minimum value of ≈ 1 W/(m·K) that is independent of temperature.

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辐照四方铝酸锂的热导率

用时域热反射（TDTR）研究了120 keV He++D+离子辐照对陶瓷四方型γ-LiAlO2在300 ~ 700 K温度下导热性能的影响。单晶γ-LiAlO2在300 K时的导热系数为13.5 W/(m·K)，随温度的变化呈1/T尺度变化。未辐照多晶γ-LiAlO2的导热系数为7.4 W/（m·K）。辐照强度为1 ×、5 ×和10 × 1016离子/cm2时，导热系数分别降低约30%、80%和90%。辐照效应在1017个离子/平方厘米时达到饱和。辐照降低了导热系数对温度的依赖性。对于大于1017个离子/cm2的离子影响，导热系数达到与温度无关的最小值≈1 W/（m·K）。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.