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SILICON CARBIDE COMPOSITE FABRICATION AND MECHANICAL AND THERMAL PERFORMANCE FOR NUCLEAR REACTOR APPLICATIONS

机译:核反应堆应用中碳化硅复合材料的制备及机械和热性能

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摘要

Chemical vapor infiltrated (CVI) silicon carbide fiber reinforced-silicon carbide matrix (SiC-SiC) composite is a relatively new material and has come under increased scrutiny as an attractive material for nuclear applications. In these materials, the interplay between fiber and matrix leads to enhanced fracture toughness. However, due to the inherent directionality of the fibers, understanding the mechanical and thermal performance is complex and requires careful characterization. At General Atomics, a laboratory has been established to develop these materials for a range of applications, in particular for the Energy Multiplier Module (EM2), which is a gas-cooled fast reactor. In this paper, the program of work that is being undertaken to fabricate and characterize SiC matrix composites is discussed. For mechanical testing, specialized fixtures have been developed to hold the thin ceramic composite specimens. For thermal testing, the purge gas species and flow rate have been identified as important parameters. Initial results on planar samples have been performed on SiC-SiC samples and hot pressed SiC samples.
机译:化学气相渗透(CVI)碳化硅纤维增强碳化硅基体(SiC-SiC)复合材料是一种相对较新的材料,作为核应用的诱人材料,受到了越来越多的审查。在这些材料中,纤维和基体之间的相互作用导致断裂韧性增强。但是,由于纤维固有的方向性,因此了解机械性能和热性能非常复杂,需要仔细表征。在General Atomics,已经建立了实验室来开发这些材料,以用于各种应用,特别是用于能量倍增模块(EM2),这是一种气冷快堆。在本文中,讨论了用于制造和表征SiC基复合材料的工作程序。对于机械测试,已经开发出专用夹具来固定薄陶瓷复合材料样品。对于热测试,已将吹扫气体的种类和流速确定为重要参数。平面样品的初步结果已在SiC-SiC样品和热压SiC样品上进行。

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  • 来源
    《Fusion Science and Technology》 |2012年第1t期|p.375-380|共6页
  • 作者单位

    General Atomics, P.O. Box 85608, San Diego, CA, 92186-5608;

    General Atomics, P.O. Box 85608, San Diego, CA, 92186-5608;

    General Atomics, P.O. Box 85608, San Diego, CA, 92186-5608;

    General Atomics, P.O. Box 85608, San Diego, CA, 92186-5608;

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