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The Qualification of Candidate Graphites for Future High Temperature Gascooled Reactors

机译:未来高温气冷堆的候选石墨资格

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摘要

1. High-Temperature Gas-Cooled Reactors (HTGRs) are graphite-moderated and helium-cooled. The graphite core components forming the moderator and reflector regions of the core assembly are subject to high fast neutron irradiation fluxes and high temperatures. These give rise to 'dimensional change' which is examined in this paper. 2. It is very important for core designers to be able to predict how the stresses within components develop as these could eventually lead to crack initiation. Therefore, there is a need for a comprehensive graphite materials database that adequately covers the dimensional change behaviour of their chosen graphite(s) and the way in which specific properties change with fast neutron irradiation.
机译:1.高温气冷堆(HTGR)是石墨调节的和氦气冷却的。形成芯组件的减速器和反射器区域的石墨芯部件要经受高快速中子辐照通量和高温的影响。这些都会引起“尺寸变化”,本文将对此进行研究。 2.对于核心设计人员来说,预测组件内部的应力如何发展非常重要,因为它们最终可能导致裂纹萌生。因此,需要一个全面的石墨材料数据库,该数据库足以覆盖其选择的石墨的尺寸变化行为以及特定性质随快速中子辐照而变化的方式。

著录项

  • 来源
    《Nuclear Energy》 |2018年第4期|50-54|共5页
  • 作者

    Mike Davies;

  • 作者单位

    Wood Group;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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