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US 4,777,009 AGranted
Automatic steam generator feedwater control over full power range
AssigneeCombustion Engineering, Inc.
InventorsGurdip Singh, Charles T. French
Life of this patent
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Abstract
A water level control for a steam generator of a pressurized water type of nuclear steam supply system varies the water level demand as a function of power. The control also varies the water feed rate after a reactor trip initially as a function of reactor coolant average temperature.
Claims17
In a pressurized water nuclear reactor steam supply system having a recirculation type steam generator including a variable speed feedwater pump, a main feedwater valve and a bypass feedwater valve, a method for controlling the water level in the steam generator comprising:
- measuring the steam flow out of the steam generator and generating a steam flow signal commensurate with the steam flow;
- measuring the feedwater flow into the steam generator and generating a feedwater flow signal commensurate with the feedwater flow;
- measuring the water level in the steam generator and generating a water level signal commensurate with the water level;
- measuring the reactor power and generating a power signal commensurate with the reactor power;
- passing the water level signal through a a first adaptive network, wherein the control coefficients in said first network have a functional form dependent on said power signal, the output of said first network representing a dynamically compensated level signal;
- comprising the steam flow signal with the feedwater flow signal and passing the difference through a first proportional/integral circuit to generate a compensated flow error signal;
- comparing the compensated level signal with the compensated flow error signal to generate a flow demand signal;
- controlling the steam generator water level as a function of said flow demand signal, through a logic scheme including three power regimes corresponding to low, intermediate, and high power levels, wherein,
- the feedwater pump speed demand is constant at low power and is modulated by the flow demand signal at intermediate and high power,
- the bypass valve position is modulated by the flow demand signal at low power, closed at intermediate power and open at high power, and
- the main valve position is closed at low power and modulated by the flow demand signal at intermediate and high power;
- whereby the operation of said feedwater pump, bypass valve and main valve determine the water level in the steam generators during operation of the nuclear steam supply system.
9 more elements
Dependencies are inferred from the claim text.