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。
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.
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。
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.
改善中心偏析关键在于控制液相穴末端的枝晶间液相的流动状况。
The control of the interdendritic flow at the end of the liquid pool is important to prevent the centreline segregation.
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