Microstructural evolution and changes in mechanical property of irradiated Fe–0.6Cu alloy under uniaxial tension stress in reactor
作者： Q. Xu , T. Yokotani , J. Zhang
DOI: 10.1080/10420150.2017.1313842
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摘要: ABSTRACTStructural materials for commercial reactor are usually used under conditions of stress. However, the evaluation microstructural evolution and changes in mechanical property induced by neutron irradiation structural does not typically consider effect stress since it is difficult to carry out testing In this study, a model alloy (Fe–0.6Cu) pressure vessels was irradiated neutrons at 573 K with dose about 3.2 × 1021 neutrons/m2 (E > 0.1 MeV), corresponding 5.2 × 10−4 dpa (displacement per atom), without tension The caused elastic deformation specimens. size microvoids sample larger than that effects on formation Cu precipitates were clear.
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