Patent Number: 042228220
Section: claims

1. A method of operating a pressurized water nuclear reactor steam generation system having a reactive core including fissile material with an axial dimension, means for controlling the axial power distribution of the core, a coolant medium and moderator for respectively removing heat from the core and slowing down neutrons in the core for fissioning, the moderator having a negative reactivity temperature coefficient, a primary coolant loop for conveying the coolant medium to a heat exchanger steam generator and a secondary loop for conveying the steam generated to a steam utilization device, including the steps of: maintaining a substantially symmetric power distribution axially throughout the core during normal reactor power operation including load follow;  operating the steam generator completely below the superheated steam region throughout normal power operation, including load follow; and  increasing the reactivity within the core and the reactor's power output without substantially altering the axial power distribution of the core, upon a given demand, by reducing the average temperature within the core, during normal reactor power operation including load follow, while maintaining a substantially constant primary coolant flow rate. 2. The method of claim 1 wherein the coolant medium is circulated into and out of the core and through a heat exchanger in a closed recycling primary system wherein the heat exchanger places the coolant medium in heat exchange relationship with water to form steam which is conveyed through a throttling valve to an exhaust and wherein the temperature of the core is reduced by increasing the amount of heat removed from the coolant medium through the heat exchanger to produce steam by increasing the amount of steam exhausted by opening the throttling valve. 3. The method of claim 2 including the step of preventing the temperature of the core from being reduced below a preselected value by limiting the opening of the throttling valve. 4. The method of claim 3 wherein the preselected value is twenty degrees Fahrenheit below the normal operating temperature of the coolant. 5. The method of claim 1 wherein the means for controlling the axial power distribution of the core includes control rods extending axially for at least the axial length of the core and movable axially into and out of the core and wherein the axial power distribution is represented by the difference in flux generated in the upper and lower halves of the core, including the step of maintaining the difference in flux generated in the upper and lower halves of the core substantially constant throughout reactor power operation by the axial positioning of the control rods. 6. The method of claim 5 including the step of preventing the control rods from being withdrawn from the core when the flux difference substantially exceeds a pre-established value. 7. The method of claim 1 wherein the coolant medium includes a neutron absorbing element wherein the reactivity increasing step further includes diluting the neutron absorbing element within the coolant medium.