Corrosion Behavior of 904L Super-austenitic Stainless Steel in Simulated Primary Water in Nuclear Power Plants
In this work,the electrochemical properties and stress corrosion cracking(SCC)behavior of 904L super-austenitic stainless steel with various kinds of microstructure in simulated primary water were studied through potentiodynamic polarization curve measurement,electrochemical impedance spec-troscopy(EIS)and U-bend immersion tests.The results show that the corrosion process of 904L stain-less steel in simulated primary water is completely controlled by electrochemical reaction.Temperature has a strong influence on the corrosion resistance of 904L stainless steel.With the increase of tempera-ture,the polarization resistance decreases;the passive range narrows down;corrosion potential shifts negatively,and corrosion resistance declines sharply.U-bend immersion test results prove that 904L stainless steel with the three kinds of microstructure has certain SCC susceptibility in simulated primary water.The corrosion products exert a two-layered structure,where the inner layer is uniform and thin black corrosion product,and the outer layer is granular and coarse white corrosion products.Among the three kinds of microstructure,the sensitized 904L stainless steel presents the highest SCC susceptibility,while solid solution treatment can decrease SCC susceptibility.
super-austenitic stainless steelstress corrosion crackingelectrochemical behaviorpri-mary waternuclear power plant
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