Abstract
Hydrogen evolution and activity release rates for stainless steel SS316 and nickel‐based Alloy 800H at the supercritical water‐cooled reactor (SCWR) conditions were estimated, together with amount of oxygen absorbed into the passivation oxide layers formed on both materials. Hydrogen evolution from an oxidized SS316 surface was found to be about six times larger than from Alloy 800H at constant temperature and pressure of 650 °C and 25 MPa. The largest 60Co activity release rate due to corrosion was estimated to be for SS316 at 650 °C and at pH10. Because of a single loop design, the radioactive corrosion products of in‐core surfaces of the SCWR are expected to be carried out‐of‐core with the supercritical coolant.
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