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Novel fabrication of silicon carbide based ceramics for nuclear applications.

机译：用于核应用的碳化硅基陶瓷的新颖制造。

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Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These materials include refractory alloys based on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as SiC--SiCf; carbon--carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor components is necessary for improved efficiency. Improving thermal conductivity of the fuel can lower the center-line temperature and, thereby, enhance power production capabilities and reduce the risk of premature fuel pellet failure.;Crystalline silicon carbide has superior characteristics as a structural material from the viewpoint of its thermal and mechanical properties, thermal shock resistance, chemical stability, and low radioactivation. Therefore, there have been many efforts to develop SiC based composites in various forms for use in advanced energy systems. In recent years, with the development of high yield preceramic precursors, the polymer infiltration and pyrolysis (PIP) method has aroused interest for the fabrication of ceramic based materials, for various applications ranging from disc brakes to nuclear reactor fuels. The pyrolysis of preceramic polymers allow new types of ceramic materials to be processed at relatively low temperatures. The raw materials are element-organic polymers whose composition and architecture can be tailored and varied.;The primary focus of this study is to use a pyrolysis based process to fabricate a host of novel silicon carbide-metal carbide or oxide composites, and to synthesize new materials based on mixed-metal silicocarbides that cannot be processed using conventional techniques. Allylhydridopolycarbosilane (AHPCS), which is an organometal polymer, was used as the precursor for silicon carbide. Inert gas pyrolysis of AHPCS produces near-stoichiometric amorphous silicon carbide (a-SiC) at 900--1150 °C. Results indicated that this processing technique can be effectively used to fabricate various silicon carbide composites with UC or UO2 as the nuclear component.
机译：核反应堆技术的进步和气冷快堆的使用要求开发能够在这些系统中预期的更高温度下运行的新材料。这些材料包括基于Nb，Zr，Ta，Mo，W和Re的耐火合金；陶瓷和复合材料，例如SiC-SiCf；碳-碳复合材料;和高级涂料。除了能够处理更高的预期温度外，反应器组件之间的有效传热对于提高效率也是必需的。改善燃料的导热性可以降低中心线温度，从而增强发电能力，并降低燃料颗粒过早失效的风险。结晶碳化硅作为一种结构材料，从其热和机械角度来看具有优越的特性。性能，抗热震性，化学稳定性和低放射性。因此，已经进行了许多努力来开发用于先进能源系统的各种形式的SiC基复合材料。近年来，随着高产陶瓷先驱物的发展，聚合物渗透和热解（PIP）方法引起了人们对制造陶瓷基材料的兴趣，这些材料用于从盘式制动器到核反应堆燃料的各种应用。预陶瓷聚合物的热解使得新型陶瓷材料可以在相对较低的温度下进行处理。原材料是元素有机聚合物，其成分和结构可以进行定制和更改。;本研究的主要重点是使用基于热解的工艺来制造大量新型的碳化硅-金属碳化物或氧化物复合物，并进行合成基于混合金属硅碳化物的新材料，无法使用常规技术进行处理。烯丙基氢化聚碳硅烷（AHPCS）是一种有机金属聚合物，被用作碳化硅的前体。 AHPCS的惰性气体热解在900--1150°C下产生接近化学计量的非晶碳化硅（a-SiC）。结果表明，该加工技术可以有效地用于制造以UC或UO2为核成分的各种碳化硅复合材料。

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