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In_situ_Synchrotron_X-ray_Investigation_of_Alloy_Corrosion_in_Supercritical_Water.pdf | 103.06 KB |
The supercritical water cooled reactor (SCWR) is one of the most promising advanced nuclear reactor designs, with a superior projected thermal efficiency compared to the currently operating light water reactors. A key barrier to the economic viability of the SCWR for electricity generation is the prevailing corrosion of the structural alloy materials in the reactor core due to the presence of supercritical water (SCW) at high temperature (up to 550oC) and pressure (25MPa). A fundamental understanding of the oxidation and ...