Comparative Safety Analysis between Supercritical Water Cooled Reactor and WWER-1000 type PWR

摘要

The supercritical water cooled reactor (SCWR) is essentially light water reactor (LWR)operating at high pressure and temperature beyond the thermodynamic critical point of water(374℃, 22.1MPa). It is a once-through direct cycle and the recirculation system is not necessary.This is the biggest difference between SCWR and LWR. The control rod, steam turbine controlvalves and reactor coolant pumps are mainly used as the power plant control system. Throughthe comparative analysis of safety characteristics during the primary pump seizure accident inSCWR and WWER-1000 type PWR, We will conclude that loss of coolant supply will lead toloss of reactor coolant flow in SCWR, but loss of coolant supply will not lead to loss of reactorcoolant flow in WWER-1000 PWR; the security configurations such as control rod, bypass valveof steam generators, the emergency feed-water pump are similar to that of SCWR; comparedwith WWER-1000 type PWR, there is a radical change of the cladding temperature on thepremise of the pressure achieving stable state rapidly, but both SCWR and WWER-1000 typePWR can build the stable natural circulation during the primary coolant pump seizure accident.