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Grain boundary impurity segregation and neutron irradiation effects in ferritic alloys

机译:铁素体合金中晶界杂质的偏析和中子辐照效应

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Segregation of alloying and impurity elements to grain boundaries in ferritic steels and alloys is known to modify the mechanical properties. This paper considers segregation of such elements, in particular phosphorus and carbon, that occur in ferritic nuclear pressure vessel steels subject to neutron irradiation and temperature typical of that encountered in service. Models are presented that allow the prediction of equilibrium and non-equilibrium segregation of phosphorus to grain boundaries and also take into account synergistic interaction with carbon under various combinations of neutron-irradiation temperature. These are related to a wide range of experimental observations compiled from data in the literature for mainly phosphorus and carbon measured at grain boundaries in neutron-irradiated ferritic vessel steels and alloys. The predictions from the segregation models are compared with these experimental data. The discussion provides a rationalization for the apparent variability in the measured grain boundary phosphorus compositions and thereby fracture susceptibility for various nuclear pressure vessel ferritic steels.
机译:众所周知,铁素体钢和合金中合金元素和杂质元素向晶界的偏析会改变机械性能。本文考虑了在受中子辐照和使用中通常遇到的温度影响的铁素体核压力容器钢中这些元素的偏析,特别是磷和碳的偏析。提出的模型可以预测磷到晶界的平衡和非平衡偏析,并且可以考虑在中子辐照温度的各种组合下与碳的协同相互作用。这些与大量的实验观察结果有关,这些观察结果是根据文献中的数据汇编而成的,这些数据主要是中子辐照的铁素体容器钢和合金在晶界处测得的磷和碳。将隔离模型的预测与这些实验数据进行比较。讨论为所测量的晶界磷成分的表观变异性以及由此对各种核压力容器铁素体钢的断裂敏感性提供了合理化。

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