Research progress of SA508Gr.3 steel for nuclear pressure vessels
Nuclear reactor pressure vessel is an important component of nuclear power plant and has the special characteristic of being non replaceable throughout its entire life cycle.The second generation of steel for nuclear pressure vessels cannot meet the use requirements due to reheat cracks found in the weld.Therefore,based on this,the SA508Gr.3 steel is improved and designed by adding Mn elements and reducing Mo and Cr elements.It has the characteristics of high strength,high toughness and low radiation embrittlement sensitivity,and is currently widely used in core components such as nuclear power pressure vessels,evaporators and regulators.This article summarizes the research progress of the SA508Gr.3 steel,focusing on the effects of alloying elements and heat treatment processes on its microstructure and mechanical properties,and provides a detailed introduction to the radiation resistance of the SA508Gr.3 steel.Based on the service environment of nuclear pressure vessels,the influence mechanism of thermal aging on the microstructure and mechanical properties of the SA508Gr.3 steel is analyzed in detail.Subsequently,the influence mechanism of microstructure evolution on its fatigue performance,fatigue crack initiation and fatigue crack propagation is summarized.Finally,the development direction and further research needed for nuclear pressure vessels are discussed,providing reference for improving the comprehensive performance of the SA508Gr.3 steel and developing the next generation of nuclear power steel.
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