核石墨耐辐照性能的评价方法

Evaluate Irradiation Behavior of Nuclear Graphite

  • 摘要: 在高温气冷堆运行过程中,作为堆内构件的石墨经受高温和快中子的辐照,会经历先收缩后膨胀的宏观尺寸形变,并在膨胀至原始尺寸时到达使用寿命。在石墨尺寸形变的过程中,石墨内部气孔的结构和数目均有明显变化。当辐照剂量接近使用寿命时,石墨内部气孔数目明显增加,导致其力学性能急剧下降而退出服役。He+、C+、Xe+离子辐照实验表明,在200 keV 1014cm-2Xe+离子辐照下,石墨气孔形貌变化明显。这一结果可作为石墨辐照性能的评价方法。

     

    Abstract: Neutron irradiation of the nuclear graphites used in high-temperature gas-cooled reactor (HTGR) results in initial bulk shrinkage at low neutron fluence followed by expansion at higher neutron fluence, and it reaches to the performance life when it expands to initial dimension. In the process of dimensional change, the structure and number of pore in nuclear graphite also change obviously. When the neutron fluence arrives at performance life, the property of nuclear graphite decreases quickly with the number of pore increasing. After He+,C+,Xe+ ions irradiation, 200 keV 1014cm-2Xe+ ions irradiation is established to evaluate the irradiation property of graphite due to changes of pore in nuclear graphite.

     

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