中子辐照引起的核反应堆压力容器钢中磷的晶间偏析是导致核反应堆压力容器脆性断裂的主要因素之一。本文提出了预测核反应堆压力容器钢中杂质元素(主要是磷)晶间非平衡偏析的溶质拖拽模型。并且与速率理论模型进行了对比。该模型的预测结果与最近发表的压力容器钢(包括C-Mn 和MnMoNi钢)的一些实验数据一致。
Neutron irradiation--induced phosphorus intergranular segregation in the reactor pressure vessel steels is the one of main reasons resulting in brittle fracture of the nuclear reactor vessel. In this paper, a solute drag model was proposed to predict the phosphorus inter granular segregation in reactor pressure vessel steels and compared with the rate theory model. The predicted results show a good agreement with experimental data recently published for pressure vessel steels (C-Mn and MnMoNi steels).
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