本技术报告介绍了与块状石墨生产、结构、化学性质、物理性质和中子辐照行为有关的基本信息。本文简要介绍了块体石墨的特性、制造、性能、辐照行为以及新一代核级石墨。本文还概述了石墨慢化气冷堆的设计。本报告是10月30日ASME锅炉及压力容器规范周期间举行的核石墨培训研讨会的总结？2006年11月3日，在肯塔基州路易斯维尔，没有普遍接受的石墨慢化剂结构设计规范。石墨慢化反应堆的历史可以追溯到从1942年开始到最近1989年的公用事业启动。在此期间的几年里，发展一直在继续，尤其是在氦冷却高温反应堆领域。棱柱状30MWth和卵石- 日本和中国分别投入了10MWT床试验反应堆的运行。

This technical report presents the basic information relative to bulk graphite production, structure, chemical properties, physical properties and neutron irradiation behavior. Bulk graphite characteristics, its manufacture, properties and irradiation behavior as well as a new generation of nuclear grades are briefly reviewed. An overview of graphite moderated gas-cooled reactor designs is also presented. The report serves as a summary of the training seminar on Nuclear Graphite conducted during the ASME Boiler and Pressure Vessel Code week, October 30?November 3, 2006, in Louisville, KY.There is no universally accepted code for the design of graphite moderator structures. The history of graphite moderated reactors is traced from the beginnings in 1942 to the most recent utility start-up in 1989. Developments have continued over the intervening years especially in the area of helium cooled High Temperature Reactors. Prismatic 30MWth, and pebble-bed 10MWth, test reactors were brought into operation in Japan and China, respectively.