Patent ID: 11955248
Assignee: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
Field: Engines, pumps, turbines (Mechanical engineering)
Classification: CPC G  Y | IPC G

Claim 0:
1. A method of limiting power of a boiling water nuclear reactor system having a reactor pressure vessel, a reactor core disposed in the reactor pressure vessel, a core shroud immediately adjacent to and surrounding the reactor core, a downcomer region immediately adjacent to and surrounding the core shroud and disposed between an inner surface of the reactor pressure vessel and the core shroud, a first steam line connected directly to an upper end of the reactor pressure vessel and to a turbine, a first condenser system receiving steam from the turbine, a second steam line not connected to a turbine, the second steam line connected directly to the upper end of the reactor pressure vessel and to a second condenser system, the second condenser system is an isolation condenser system that is separate from the first condenser system, wherein steam from the reactor pressure vessel passes through the second steam line to the second condenser system, the method comprising:
returning condensate from the first condenser system and the second condenser system to release the condensate at a location inside the core shroud directly vertically above the reactor core into a middle elevation of a chimney region of the core shroud; and
wherein the returning returns the condensate from the first condenser system through a first condensate return line that returns the condensate inside the core shroud and that includes a first split portion that returns condensate inside the downcomer region and wherein the returning returns the condensate from the second condenser system through a second condensate return line that returns the condensate inside the core shroud and that includes a second split portion that returns condensate inside the downcomer region.