Transmission Electron Microscopy Study of Graphite under in situ Ion Irradiation
Transmission Electron Microscopy Study of Graphite under in situ Ion Irradiation
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原位离子辐照下石墨的透射电子显微镜研究
DOI：
10.1088/1742-6596/371/1/012046
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发表时间：
2012
期刊：
影响因子：
--
通讯作者：
Hinks J
中科院分区：
文献类型：
--
作者：
Hinks J
英国 18 个 Magnox 和先进气冷反应堆 (AGR) 中均采用石墨作为慢化剂和结构部件。在反应堆的运行寿命期间，由于温度、氧化和辐照引起的原子位移的影响，石墨会经历复杂的物理和机械性能变化，包括尺寸变化。为了安全地延长现有 AGR 的使用寿命，并为超高温反应堆 (VHTR) 等 GenIV 概念开发材料，更好地了解支撑石墨在当前和未来运行条件下行为的基本原子过程非常重要。
Graphite is employed as a moderator and structural component in 18 of the UK's fleet of Magnox and Advanced Gas-cooled Reactors (AGRs). During the operational lifetime of a reactor, graphite undergoes complex physical and mechanical property changes including dimensional modification, owing to the effects of temperature, oxidation and irradiation-induced atomic displacements. In order to safely extend the lifetime of the current fleet of AGRs, and also to develop materials for GenIV concepts such as the Very-High-Temperature Reactor (VHTR), it is important to gain a better understanding of the fundamental atomic processes which underpin the behaviour of graphite under current and future operational conditions.