The thermal circuit of a nuclear power station’s unit built around a supercritical-pressure water-cooled reactor

Main results obtained from calculations of the steam generator and thermal circuit of the steam turbine unit for a nuclear power unit with supercritical-pressure water coolant and integral layout are presented. The obtained characteristics point to the advisability of carrying out further developments of this promising nuclear power technology.     

Water chemistry of the system for cooling the electrical generator’ stator of the power unit at a thermal power station

Results from studies of the water chemistry used in the system for cooling the stator windings of alternators used in supercritical-pressure power units are presented, and a solution is suggested using which the standardized pH value of cooling water is maintained in the range 8.0–9.0. It is shown that addition of NaOH in the water cooling system when a drop of pH value occurs cannot fully satisfy the requirements of the operating circular due to low buffer properties of aqueous medium.