[en] The new designs that characterize the next generation of nuclear reactors promise considerable improvements in the areas of efficiency and simplification in the plant layout. One promising technology that is being considered in Canada is the CANDU®-Supercritical Water-cooled Reactor (SCWR), a potential addition to the CANDU® fleet of reactors. To harness the thermodynamic advantages of operating with a supercritical coolant, advanced materials are required that can withstand these extreme conditions. In this study, three commercially available alloys are exposed to supercritical water in the flow loop at UNB; 304SS, HC276 and I625 were all tested to establish a corrosion baseline using materials readily available and in use in a variety of fields. Additionally, two ferritic steels were cast in conjunction with CANMET-MTL. A 14% chromium alloy is being considered as a base material for processing to an oxide dispersion strengthened (ODS) steel; a 25% chromium alloy has been developed as a potential corrosion resistant coating. The commercially available alloys behaved as expected with corrosion rates similar to previous work found in literature. Useful information was provided by the ferritic steel exposures. Weight change data were verified with SEM imaging for both the 14-Cr and 25-Cr alloys. The 14% chromium base material formed a continuous two-layer oxide, which grew with time; the 25% chromium coating alloy showed a good resistance to corrosion with minimal weight change observed.