型试样在核反应堆压力容器用材料的断裂韧度测试中具有良好的应用前景。
The W-type specimen has a well prospective application in the measurement of fracture toughness of the materials which are used in the nuclear reactor.
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.
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.
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