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Characterization of Damaged Epoxy Resins on Steel Liners OriginatedOperation of Nuclear Power Plant

机译:核电站运行中钢衬上受损环氧树脂的表征

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摘要

The property chm~ges of epoxy coatings on steel plate in atomic reactor container have been mmlyzed in terms ofrnthermal properties in the case of simple irradiation and designed accident conditions (DBA: design basis accident). Twornkinds of the epoxy coating systems were selected in this work. The specimens were irradiated by two different dose rates,rni.e., 1×10~6 and 5×10~5 rad. The total dosage was fixed at 2×10~8 rad. Two kinds of DBA conditions were applied in thernspecimens. Their effects have been surveyed in the context of the clmnges of glass transition tenlperature (T_g), the initialrndecomposition temperatures (T_(IDT)), and the maximum decomposed temperature (T_(max)). As a result, the different epoxyrnsystems, irradiation rates, and DBA test conditions showed a significant change on the thermal properties of thernspecimens.
机译:在简单辐照和设计事故条件(DBA:设计基准事故)的情况下,就原子热反应器中钢板的环氧涂层的性能变化进行了热分析。在这项工作中选择了两种环氧涂料体系。标本分别以1×10〜6 rad和5×10〜5 rad的两种剂量率辐照。总剂量固定为2×10〜8 rad。在样本中应用了两种DBA条件。在玻璃化转变温度(T_g),初始分解温度(T_(IDT))和最大分解温度(T_(max))的背景下调查了它们的影响。结果,不同的环氧体系,辐照速率和DBA测试条件显示了标本的热性能发生了显着变化。

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  • 来源
  • 会议地点 Washington DC(US);Washington DC(US)
  • 作者单位

    Advanced Materials Division, Korea Research Institute of Chemical Technology, P.O. Box 107, Yusong, Taejon 305-rn600, Korea;

    Advanced Materials Division, Korea Research Institute of Chemical Technology, P.O. Box 107, Yusong, Taejon 305-rn600, Korea;

    Advanced Materials Division, Korea Research Institute of Chemical Technology, P.O. Box 107, Yusong, Taejon 305-rn600, Korea;

    Structural Systems Site Evaluation Dept., Korea Institute of Nuclear Safety, Yusong, Taejon 305-338, Korea;

    Structural Systems Site Evaluation Dept., Korea Institute of Nuclear Safety, Yusong, Taejon 305-338, Korea;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 核反应堆工程;
  • 关键词

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