| Advanced supercritical water cooled nuclear reactors require materials to survive a corrosive, high temperature fluid environment, in addition to radiation effects. This thesis details corrosion testing of A286 (iron-nickel based), AISI 310 stainless steel, and IN625 (nickel based) in supercritical water (29 MPa) and superheated steam (ambient pressure) at 650°C to understand effects of materials' composition and fluid pressure.;A286 demonstrated poor corrosion resistance due to low chromium content. AISI 310 and IN625 demonstrated similarly strong corrosion resistance in supercritical water through formation of adherent scales, but poor corrosion resistance in superheated steam due to scale spallation. Supercritical water and superheated steam corrosion behaviour were non-analogous.;A superheated steam testing rig was designed and an autoclave was assembled. Samples were tested for 100, 200, and 300 hours, then analysed for weight gain and surface appearance; surface morphology and composition were determined through scanning electron microscope imaging and energy-dispersive X-ray spectroscopy. |
