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In the case of a loss of coolant accident (LOCA), the water-loss of the primary cooling system can be compensated with normal water pumped into the cooling circuit. On the other hand, the standby liquid control (SLC) system (SLCS) consists of a solution containing boric acid , which acts as a neutron poison and rapidly floods the core in case ...
The Russian abbreviation VVER stands for 'water-water energy reactor' (i.e. water-cooled water-moderated energy reactor). The design is a type of pressurised water reactor (PWR). The main distinguishing features of the VVER [3] compared to other PWRs are: Horizontal steam generators; Hexagonal fuel assemblies; No bottom penetrations in the ...
Standby generators. A standby generator is a back-up electrical system that operates automatically. [1] Within seconds of a utility outage an automatic transfer switch senses the power loss, commands the generator to start and then transfers the electrical load to the generator. The standby generator begins supplying power to the circuits. [2]
The Reactor Protection System (RPS) is a system, computerized in later BWR models, that is designed to automatically, rapidly, and completely shut down and make safe the Nuclear Steam Supply System (NSSS – the reactor pressure vessel, pumps, and water/steam piping within the containment) if some event occurs that could result in the reactor entering an unsafe operating condition.
The coolant flow for each turbine is 82,880 t (91,360 short tons)/h. The generator produces 20 kV 50 Hz AC power. The generator's stator is cooled by water while its rotor is cooled by hydrogen. The hydrogen for the generators is manufactured on-site by electrolysis. [15]
Supercritical water exists at temperatures above 374 °C and pressures above 220 atmospheres. Diagram of a supercritical water-cooled nuclear reactor. A supercritical steam generator is a type of boiler that operates at supercritical pressure and temperature, frequently used in the production of electric power.