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Volume 28 Issue 5
Oct.  2007
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LUO Xiao-wei, YU Xin-li, YU Su-yuan. Oxidation Performance of Graphite Material Used in Reactor[J]. Nuclear Power Engineering, 2007, 28(5): 50-53,98.
Citation: LUO Xiao-wei, YU Xin-li, YU Su-yuan. Oxidation Performance of Graphite Material Used in Reactor[J]. Nuclear Power Engineering, 2007, 28(5): 50-53,98.

Oxidation Performance of Graphite Material Used in Reactor

  • Received Date: 2006-06-07
  • Rev Recd Date: 2007-04-27
  • In high temperature gas-cooled reactor(HTGR),graphite is used as structural materials and moderator.During reactor operating,graphite oxidation which influences the safety and operation of reactor occurs due to the impurities in coolant or water ingress accident and air ingress accident which may be take place.In this paper,the oxidation process of graphite was introduced firstly,and then the factors which influence the graphite oxidation were analyzed and discussed.Some new questions for further studing were given.

     

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