孔隙率和合金元素对钨基复合材料导热性能的影响

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-04-09 DOI:10.1016/j.jnucmat.2025.155817

Oleksii Popov , Vladimir Vishnyakov

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引用次数: 0

摘要

通过直接热流测量评估了烧结钨和钨基 W-C、W-C-Y2O3 和 W-C-Cu 复合材料的导热系数。孔隙率从 5% 增加到 16%，再加上晶粒尺寸的减小，纯钨的热导率从 146 W/mK 降到了 110 W/mK。钨晶界热绝缘性被评估为 YW-W = 6-10-9 m2K/W。热压过程中在钨晶粒上形成的 W2C 层是导致热导率下降的原因。经计算，W-W2C 边界热绝缘度为 YW-W2C = 13.5-10-9 m2K/W，这对降低 W-W2C 材料的热导率至关重要。由于晶界热绝缘，复杂的钨基复合材料很可能会大大降低热导率。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

The influence of porosity and alloying elements on tungsten-based composites thermal conductivity

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The influence of porosity and alloying elements on tungsten-based composites thermal conductivity

The thermal conductivity coefficients of sintered tungsten and tungsten-based W-C, W-C-Y₂O₃, and W-C-Cu composites were evaluated via direct heat flow measurements. Porosity increase from 5 to 16 % in combination with the grain size reduction has lowered pure tungsten thermal conductivity from 146 W/mK to 110 W/mK. Tungsten grain boundary thermal insulance has been evaluated as Y_W-_W = 6·10^–9 m²K/W.

Adding 1.9 wt. % of carbon decreased tungsten thermal conductivity by 80 % to 29 W/mK. This decrease was shown to be caused by the W₂C layer forming on the W grains during the hot pressing. The W-W₂C boundary thermal insulance was calculated as Y_W-W2C = 13.5·10^–9 m²K/W and was shown to be crucial in low W-W₂C material thermal conductivity. Complex tungsten-based composites will most likely have significantly reduced thermal conductivity due to the grain boundary thermal insulances.

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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.