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Effects of Displacing Radiation on Graphite Observed Using in situ Transmission Electron Microscopy

机译:用原位透射电子显微镜观察辐射对石墨的影响

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Graphite is used as a moderator and structural component in the United Kingdom's fleet of Advanced Gas-Cooled Reactors (AGRs) and features in two Generation IV reactor concepts: the Very High Temperature Reactor (VHTR) and the Molten Salt Reactor (MSR). Under the temperature and neutron irradiation conditions of an AGR, nuclear-grade graphite demonstrates significant changes to it mechanical, thermal and electrical properties. These changes include considerable dimensional change with expansion in the c-direction and contraction in the a/b-directions. As the United Kingdom's AGRs approach their scheduled decommissioning dates, it is essential that this behaviour be understood in order to determine under what reactor conditions their operating lifetimes can be safely extended. Two models have been proposed for the dimensional change in graphite due to displacing radiation: the "Standard Model" and "Ruck and Tuck". The Standard Model draws on a conventional model of Frenkel pair production, point defect migration and agglomeration but fails to explain several key experimental observations. The Ruck and Tuck model has been proposed by M.I. Heggie et at. and is based upon the movement of basal dislocation to create folds in the "graphene" sheets and seeks not only to account for the dimension change but also the other phenomena not explained by the Standard Model. In order to test the validity of these models, work is underway to gather experimental evidence of the microstructural evolution of graphite under displacing radiation. One of the primary techniques for this is transmission electron microscopy with in situ ion irradiation. This paper presents the results of electron irradiation at a range of energies (performed in order to separate the effects of the electron and ion beams) and of combined electron and ion beam irradiation.
机译:Graphite被用作英国先进的气冷反应堆(AGRS)的主持人和结构部件(AGRS),以及两代IV反应器概念:非常高温反应器(VHTR)和熔盐反应器(MSR)。在AGR,核级石墨的温度和中子辐射条件下,表明IT机械,热和电性能的显着变化。这些变化包括相当大的尺寸变化,在C方向上的膨胀和A / B方向上的收缩。随着英国的农业接近其预定的退役日期,必须了解这种行为,以便根据反应堆条件可以安全地延长它们的操作寿命。已经提出了两种模型,用于由于位移辐射而导致的石墨中的尺寸变化:“标准型号”和“喇叭和折叠”。标准模型借鉴了Frenkel对生产,点缺陷迁移和凝聚的传统模型,但未能解释几个关键的实验观察。 Ruck和Tuck模型已被M.I提出。哈吉等。并且基于基于基础脱位的运动,在“石墨烯”床单中产生褶皱,并且不仅旨在考虑维度变化,而且还不仅是由标准模型解释的其他现象。为了测试这些模型的有效性,正在进行工作来收集辐射下石墨微观结构演化的实验证据。其中一个主要技术是具有原位离子辐射的透射电子显微镜。本文介绍了一系列能量的电子照射的结果(以便分离电子和离子束的效果)和组合电子和离子束照射。

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