中文摘要：

因为炭材料具有热膨胀系数低、抗热冲击性好、中子活化性能低等优异的性能，是核反应堆（特别是高温气冷堆）不可缺少的慢化、反射和结构材料。本文综合分析炭材料的核物化性能，重点剖析了核石墨的材料类型和制备方法。提出采用化学与物理并用的方法，去除炭石墨原料、大尺寸石墨块体的杂质，有可能使炭材料达到核石墨纯度要求；采用编织和化学沉积等复合材料技术制备炭／炭复合材料，制造核反应堆热结构件；采用热等静压工艺技术和振动成型制备各向同性石墨材料和核石墨块，并在2800～3000℃进行高温石墨化处理。采用先进的电子显微学、同步辐射等技术，研究核石墨的结构和性能，特别是其在中子辐射条件下的性能特征和行为特性，在此基础上，制定和建立科学合理的核石墨生产工艺流程、工艺技术条件。

英文摘要：

Due to low coefficient of thermal expansion（CTE）, excellent thermal shock resistance and low neutron activation, carbon materials are employed as the neutron moderator, reflector and structural components in nuclear reactors, particularly high- temperature gas- cooled reactor. In this paper the physical and chemical properties, materials style and production methods of nuclear graphite are introduced. It was indicated that nuclear reactor grade graphite and blocks could be purified by combining the physical and chemical methods. Carbon/carbon materials could be produced by processing of dimensional weave of carbon fibers and chemical densifieation for hot structural components. Nuclear graphite blocks can be produced by isostatic and vibratory compaction techniques and heated from 2 800 to 3 000 ℃. Their microstructure and properties should be detected by electronic microscopy and synchrotron radiation, particularly their performance in synchrotron neutron radiation condition. With the detections of structure and properties, graphite materials can be produced by suitable production processing and conditions and used in high temperature gas cooled reactors.