Effect Of Pressure On The Corrosion Of Materials In High Temperature Water

One of the major challenges for the Canadian Gen IV Super-Critical Water-cooled Reactor (SCWR) concept is the selection of fuel cladding materials. The Canadian SCWR concept will operate at a core outlet temperature of 625 oC and 25 MPa of pressure with peak cladding temperature reaching as high as 800 oC. Corrosion resistance is an important factor for material selection. Austenitic stainless steels that contain Cr contents greater than 18 wt.% are generally considered to provide adequate corrosion resistance. In this work, the pressure dependence of the corrosion of austenitic stainless steel 310 containing 24 wt% Cr is assessed at 625 C for exposures of 1000 hours to evaluate the suitability of superheated steam as a surrogate for supercritical water at 25 MPa. Transmission Electron Microscopy (TEM) revealed that 310 exposed to different pressure conditions at 625 oC. (i.e., 0.1, 8 and 29 MPa) had generally the same type of the oxide structure, i.e., a Cr-rich oxide with the spinel structure on outer surface adjacent to the water phase. The material exposed at 8 and 29 MPa had a double layer oxide structure, with the outer oxide layer having a much larger grain size, while the samples exposed at 0.1 MPa showed only a single spinel-phase oxide layer. Cr-depleted recrystallized austenite grains were found underneath the spinel phase oxide. The adjacent large-grained austenite substrate had M23C6 carbides in the grain interior. The implications of these results are discussed.