Abstract
Large polygon bubbles can cause significant swelling and embrittlement in irradiated materials. Understanding their formation and growth process is thus important to alleviate the mechanical property degradation of nuclear materials. Here, based on in-situ 30 keV H2+ and He+ synergetic irradiation in Fe9Cr1.5W0.4Si ferritic/martensitic steels, polygonal bubble evolution was investigated at grain boundaries, matrix-precipitate interfaces and matrices. Two threshold sizes were first found for bubble growth in the matrix. One determined the shape between sphere and rectangle, while the other determined whether growth was continuous or reached a saturation size. Large polygonal bubbles formed at interfaces due to abnormal growth rates and coalescence between bubbles. Finally, the bubble growth at sinks and matrices was explained using a bubble growth rate model.
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