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APPLICATION OF AL-B_4C METAL MATRIX COMPOSITES IN THE NUCLEAR INDUSTRY FOR NEUTRON ABSORBER MATERIALS

机译:AL-B_4C金属基复合材料在核工业中子吸收材料中的应用

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摘要

For dry storage and transport of spent nuclear fuel in the nuclear industry, the most commonly used neutron absorbers are boron-containing metallic materials, in which the boron element possesses a high cross-section for absorbing thermal neutrons. Al-B_4C Metal Matrix Composites (MMCs), recently developed by Alcan, are particularly suitable for manufacturing high quality neutron absorber components due to the flexibility of adding various boron concentrations, the lightweight, the superior thermal conductivity and the mechanical properties. In this paper, the process route for manufacturing Al-B_4C composites and the technical challenge are presented. Results of neutron absorption based on neutron transmission testing for typical Al-B_4C composites produced in the industrial scale are described. A series of Al-B_4C MMCs with different Al-matrix alloys and B_4C loads are introduced for both structural and non-structural applications. The composites can be cast, extruded or rolled to almost any desired size and shape. The typical microstructure, mechanical properties and thermal conductivity of some Al-B_4C products are reported.
机译:对于核工业中乏核燃料的干燥存储和运输,最常用的中子吸收器是含硼金属材料,其中硼元素具有高截面以吸收热中子。 Alcan最近开发的Al-B_4C金属基复合材料(MMC)由于添加各种硼浓度的灵活性,重量轻,优异的导热性和机械性能而特别适合于制造高质量的中子吸收体组件。本文介绍了制备Al-B_4C复合材料的工艺路线和技术挑战。描述了基于中子传输测试的工业规模生产的典型Al-B_4C复合材料的中子吸收结果。针对结构和非结构应用,引入了一系列具有不同Al-基体合金和B_4C载荷的Al-B_4C MMC。可以将复合材料浇铸,挤压或轧制成几乎任何所需的尺寸和形状。报告了一些Al-B_4C产品的典型组织,力学性能和导热系数。

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