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Effects of Oxide Additions on the Corrosion Behaviour of Cr2O3 Based Ceramics in High Temperature Supercritical Water EnvironmentDownload
This investigation is aimed at developing ceramic materials applied in supercritical water, which is being considered as coolant for one of the next generation nuclear reactors. Cr2O3, a primary protective film on stainless steels, was found to be unstable in SCW due to the formation of soluble...
As the Supercritical Water-cooled Reactor (SCWR) shows a promising future, the corrosion behavior of candidate materials has attracted great interest. In this study, experimental investigation was conducted to evaluate the corrosion behavior of the ferritic-martensitic steels designed for the use...
The present research has been done with the intent of evaluating the corrosion resistance and cracking susceptibility of some commercial candidate alloys that can be potentially used in Gen-IV supercritical water reactor (SCWR). The mechanism of the crack initiation in austenitic alloys exposed...