In the PGSFR, SWR events are included in the design-basis event. ![]() ![]() When a sodium–water reaction (SWR) occurs due to leakage or breakage of steam generator tubes, high-pressure waves and corrosive reaction products are produced, which threaten the structural integrity of the components of the intermediate heat-transfer system (IHTS) and the safety of the primary heat-transfer system (PHTS). ![]() Sodium has chemical characteristics that allow it to violently react with materials such as a water or steam. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine. ![]() The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute.
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