Patent Number: 
Section: claims

1. A method for controlling a power level of a natural circulation boiling water nuclear reactor (NCBWR), comprising:sensing a temperature of a feedwater flowing into a reactor annulus of the NCBWR, the sensing performed with a temperature sensor;controlling the power level generated by a core of the NCBWR based on the temperature sensed by the temperature sensor, the controlling including adjusting the temperature of the feedwater flowing into the reactor annulus, the adjusting performed with a heating subsystem of the NCBWR; andreceiving high temperature steam at the heating subsystem via a steam diversion line, the high temperature steam coming directly from a steam header of the NCBWR. 2. The method of claim 1, wherein controlling the power level includes:transferring the high temperature steam to the steam header of the NCBWR, the high temperature steam being generated by the core;introducing an input flow of the feedwater to at least one supplemental feedwater heater of the heating subsystem and supplying an output flow of the feedwater from the at least one supplemental feedwater heater to the reactor annulus, the heating subsystem being downstream of one or more principal feedwater heaters;providing the high temperature steam from the steam header to the at least one supplemental feedwater heater via a steam bypass valve in the steam diversion line, the steam bypass valve configured to receive commands from a temperature controller communicatively connected to the temperature sensor and, based on the received commands, control an amount of the high temperature steam from the steam header into the at least one supplemental feedwater heater to increase the temperature of the output flow of the feedwater to the reactor annulus to a new target temperature, the new target temperature being higher than a current target temperature. 3. The method of claim 2, wherein the controlling the power level further includes the at least one supplemental feedwater heater of the heating subsystem configured to receive the input flow of feedwater from the one or more principal feedwater heaters of the NCBWR separate from the heating subsystem, the one or more principal feedwater heaters configured to heat the feedwater to the current target temperature, the at least one supplemental feedwater heater configured to heat the feedwater to the new target temperature. 4. The method of claim 2, wherein the one or more principal feedwater heaters includes a plurality of principal feedwater heaters, the controlling the power level further comprises:transferring steam from one of a high pressure turbine and a moisture separator reheater to the plurality of principal feedwater heaters to heat the feedwater flowing into the reactor annulus to the current target temperature; andtransferring the high temperature steam from the steam header to the plurality of principal feedwater heaters, via the steam bypass valve in the steam diversion line, to increase the temperature of the feedwater to the reactor annulus to the new target temperature to reduce a power output of the core. 5. The method of claim 2, wherein the one or more principal feedwater heaters includes a plurality of principal feedwater heaters, and wherein controlling the power level further comprises:transferring steam from one of a high pressure turbine and a moisture separator reheater to at least one of the principal feedwater heaters to heat the feedwater flowing into the reactor annulus to the current target temperature; andtransferring the high temperature steam from the steam header to at least one of the principal feedwater heaters of the NCBWR separate from the heating subsystem to heat the feedwater flowing into the reactor annulus to the current target temperature and to increase the temperature of the feedwater flowing into the reactor annulus to the new target temperature when a reduction in core output power is desired. 6. The method of claim 2, wherein controlling the power level further comprises:controlling an amount of flow of the feedwater through a heater bypass line into the reactor annulus, utilizing a feedwater bypass valve operable to receive commands from the temperature controller, to decrease the temperature of the feedwater flowing into the reactor annulus to a new target temperature to increase the power level generated by the core; andreceiving the input flow of feedwater at the at least one supplemental feedwater heater of the heating subsystem from the one or more principal feedwater heaters of the NCBWR separate from the heating subsystem, where the feedwater flow is heated by the high temperature steam to the new target temperature. 7. The method of claim 2, wherein the one or more principal feedwater heaters includes a plurality of principal feedwater heaters separate from the heating subsystem, and wherein the method further comprises:controllably transferring steam from one of a high pressure turbine and a moisture separator reheater to the principal feedwater heaters to heat the feedwater flowing into the annulus to a temperature above the current target temperature;utilizing a feedwater bypass valve operable to receive commands from a temperature controller communicatively connected to the temperature sensor, to control an amount of feedwater flowing through a heater bypass line into the reactor annulus to increase the temperature of the feedwater flowing into the reactor annulus from the principal feedwater heaters to a temperature above the current target temperature when a reduction in reactor core output power is desired; andutilizing the feedwater bypass valve to control the amount of feedwater flowing through the heater bypass line into the reactor annulus to decrease the temperature of the feedwater flowing into the annulus from the principal feedwater heaters to a temperature below the current target temperature when an increase in reactor core output power is desired. 8. The method of claim 1, wherein the controlling the power level comprises utilizing a heating device operable to receive commands from a temperature controller communicatively connected to the temperature sensor and based on the received commands increase the temperature of feedwater flowing through a feedwater line from at least one principal feedwater heater of the NCBWR to the reactor annulus. 9. The method of claim 1, wherein the heating subsystem includes a steam bypass valve in the steam diversion line, the steam bypass valve being configured to control a flow of the steam in the steam diversion line. 10. The method of claim 9, wherein the steam received by the steam diversion line has not passed through a turbine. 11. The method of claim 9, wherein the controlling controls the steam bypass valve of the heating subsystem. 12. The method of claim 1, wherein the core of the NCBWR does not include a forced recirculation flow.