球化天然鳞片石墨基各向同性石墨的超低热膨胀系数

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2024-12-03 DOI:10.1016/j.jnucmat.2024.155544
Xinlei Cao , Kun Xu , Yanan Niu , Shen Lv , Ke Shen
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引用次数: 0

摘要

随着高温气冷堆的发展,核级石墨的热膨胀系数(CTE)在反应堆设计中起着越来越重要的作用。较低的CTE提高了石墨芯结构的完整性和反应堆效率。本文提出了一种利用球化天然鳞片石墨(SFG)作为填充材料,具有低CTE的新型各向同性石墨牌号。SFG基石墨的超低各向同性CTE值为2.6 ~ 2.9 × 10−6 K−1,这是由于SFG颗粒内部的狭缝状孔隙能够适应平面热膨胀。为了提高硫化石墨的焙烧性能,采用硫化石墨/焦炭或硫化石墨/微晶石墨(MG)的混合填料防止坯体开裂。特别是MG的加入可以在不改变sfg基石墨低CTE值的情况下防止开裂。这项研究有助于开发具有低CTE的新型石墨材料,可用于核工程,半导体工业和其他高温环境。
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Utralow coefficient of thermal expansion in a spheroidized natural flake graphite based isotropic graphite
With the development of high-temperature gas-cooled reactors, the coefficient of thermal expansion (CTE) of nuclear-grade graphite plays an increasingly important role in reactor design. A lower CTE enhances both the integrity of the graphite core structure and reactor efficiency. In this paper, we present a new isotropic graphite grade with a low CTE, utilizing spheroidized natural flake graphite (SFG) as a filler material. The ultralow isotropic CTE of 2.6–2.9 × 10−6 K−1 in the SFG-based graphite, owing to the ability of the slit-shaped pores within the SFG particles to accommodate cross-plane thermal expansion. To enhance the baking performance of the SFG-based graphite, hybrid fillers of SFG/coke or SFG/microcrystalline graphite (MG) were used to prevent cracking of the green bodies. In particular, the addition of MG prevents cracking without changing the low CTE value of the SFG-based graphite. This research contributes to the development of new graphite materials with low CTE that can be used in nuclear engineering, the semiconductor industry, and other high-temperature environments.
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来源期刊
Journal of Nuclear Materials
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.
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