Electricity and steam generation from a helium-cooled nuclear reactor

A system for producing electricity and steam comprising:

• a Brayton power conversion cycle employing helium as a working fluid in a first closed loop wherein the first closed loop comprises:
• a heat source comprising a nuclear reactor;
• wherein a core of the nuclear reactor is cooled using helium;
• a power conversion system comprising a turbine, a compressor, and an electrical generator, wherein the compressor, the turbine, and the electrical generator are in operative communication with each other;
• wherein the turbine is located downstream from the heat source and is in fluid communication with the heat source, and the turbine is a high pressure turbine that receives helium at a pressure in the range of about 50 to about 90 kg/cm2;
• a heat recovery steam generator, located downstream of the turbine and in fluid communication with the turbine, where the steam generated is at a pressure that is less than or equal to about the pressure of the helium in the first closed loop;
• and
• a waste heat removal heat exchanger, located downstream of the heat recovery steam generator and in fluid communication with the heat recovery steam generator wherein, the heat recovery steam generator is operative to extract heat from helium and superheat the steam to a temperature of about 200 to 400° C. and a pressure of about 4 to about 12 kg/cm2.