CN109681443B - Rotation speed control system and method for steam-driven main feed pump of nuclear power station - Google Patents
Rotation speed control system and method for steam-driven main feed pump of nuclear power station Download PDFInfo
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- CN109681443B CN109681443B CN201811383956.9A CN201811383956A CN109681443B CN 109681443 B CN109681443 B CN 109681443B CN 201811383956 A CN201811383956 A CN 201811383956A CN 109681443 B CN109681443 B CN 109681443B
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04D—NON-POSITIVE-DISPLACEMENT PUMPS
- F04D15/00—Control, e.g. regulation, of pumps, pumping installations or systems
- F04D15/0066—Control, e.g. regulation, of pumps, pumping installations or systems by changing the speed, e.g. of the driving engine
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D17/00—Regulating or controlling by varying flow
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04D—NON-POSITIVE-DISPLACEMENT PUMPS
- F04D15/00—Control, e.g. regulation, of pumps, pumping installations or systems
- F04D15/0077—Safety measures
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04D—NON-POSITIVE-DISPLACEMENT PUMPS
- F04D15/00—Control, e.g. regulation, of pumps, pumping installations or systems
- F04D15/02—Stopping of pumps, or operating valves, on occurrence of unwanted conditions
- F04D15/0281—Stopping of pumps, or operating valves, on occurrence of unwanted conditions responsive to a condition not otherwise provided for
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F05—INDEXING SCHEMES RELATING TO ENGINES OR PUMPS IN VARIOUS SUBCLASSES OF CLASSES F01-F04
- F05D—INDEXING SCHEME FOR ASPECTS RELATING TO NON-POSITIVE-DISPLACEMENT MACHINES OR ENGINES, GAS-TURBINES OR JET-PROPULSION PLANTS
- F05D2260/00—Function
- F05D2260/80—Diagnostics
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F05—INDEXING SCHEMES RELATING TO ENGINES OR PUMPS IN VARIOUS SUBCLASSES OF CLASSES F01-F04
- F05D—INDEXING SCHEME FOR ASPECTS RELATING TO NON-POSITIVE-DISPLACEMENT MACHINES OR ENGINES, GAS-TURBINES OR JET-PROPULSION PLANTS
- F05D2270/00—Control
- F05D2270/01—Purpose of the control system
- F05D2270/02—Purpose of the control system to control rotational speed (n)
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F05—INDEXING SCHEMES RELATING TO ENGINES OR PUMPS IN VARIOUS SUBCLASSES OF CLASSES F01-F04
- F05D—INDEXING SCHEME FOR ASPECTS RELATING TO NON-POSITIVE-DISPLACEMENT MACHINES OR ENGINES, GAS-TURBINES OR JET-PROPULSION PLANTS
- F05D2270/00—Control
- F05D2270/30—Control parameters, e.g. input parameters
- F05D2270/304—Spool rotational speed
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F05—INDEXING SCHEMES RELATING TO ENGINES OR PUMPS IN VARIOUS SUBCLASSES OF CLASSES F01-F04
- F05D—INDEXING SCHEME FOR ASPECTS RELATING TO NON-POSITIVE-DISPLACEMENT MACHINES OR ENGINES, GAS-TURBINES OR JET-PROPULSION PLANTS
- F05D2270/00—Control
- F05D2270/70—Type of control algorithm
- F05D2270/706—Type of control algorithm proportional-integral-differential
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- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Control Of Turbines (AREA)
- Testing And Monitoring For Control Systems (AREA)
Abstract
The invention provides a system and a method for controlling the rotating speed of a steam-driven main feed water pump of a nuclear power station, wherein the system comprises a digital controller, a trip protection circuit, a driver, an actuator and two rotating speed sensors; the two rotation speed sensors respectively acquire the rotation speed of the steam-driven main water feeding pump, generate corresponding rotation speed pulse signals and transmit the rotation speed pulse signals to the digital controller; the digital controller determines an actually measured rotating speed value of the steam-driven main water feeding pump according to two rotating speed pulse signals corresponding to the two rotating speed sensors, generates a corresponding control signal according to the actually measured rotating speed value and a given rotating speed signal, and transmits the control signal to the driver; the driver generates corresponding driving current according to the control signal and the feedback signal of the actuator, outputs the driving current to the actuator, and drives the actuator to act so as to adjust the valve opening of the steam regulating valve. The invention can improve the precision of the rotation speed regulation of the steam-driven main feed water pump and optimize the reliability of the rotation speed control system.
Description
Technical Field
The invention relates to the technical field of nuclear power stations, in particular to a system and a method for controlling the rotating speed of a steam-driven main feed water pump of a nuclear power station.
Background
In the design of a nuclear power station process system, a main water supply system is used for supplying water to a steam generator, and the pressure difference between a water supply main pipe and a steam main pipe of the steam generator is ensured to be equal to a setting value which changes along with a group load, so that the front-back differential pressure of a regulating valve of a water supply flow control system is kept approximately constant, and the water supply flow requirement of the steam generator is met. The main water supply flow control of the evaporator is a cascade PID closed loop regulating system, and the inner loop of the main water supply flow control of the evaporator is a PID control system taking the rotating speed of a steam-driven main water supply pump as a control target. In the cascade PID closed-loop regulation system, the inner-loop PID plays a crucial role in the rapidity of the response of the cascade PID closed-loop regulation system.
In a part of the steam-driven main water supply systems of the nuclear power plants, a complete rotating speed control system of a steam-driven main water supply pump comprises a starting control subsystem and a loaded speed regulating subsystem. As shown in fig. 1, the start control subsystem controls the start valve by a Programmable Logic Controller (PLC), the electrical converter (EP) with the speed regulation subsystem and the mechanical governor control steam regulating valve (the extraction valve 1, the extraction valve 2 and the new steam valve are all steam regulating valves, and when the steam regulating valve is regulated, one of the three steam regulating valves can be selected for regulation). Before the rotation speed control system is started, the steam regulating valve is in a closed position, the starting valve is in a full-open position, the rotation speed given value corresponding to the given rotation speed signal is 4mA, and the signal oil pressure is smaller than the opening threshold values of all the steam regulating valves. After the programmable controller finishes the self-checking of the starting of the steam-driven main water-feeding pump, the starting valve is started to be controlled to gradually close the opening, the pressure of the signal oil gradually rises, the steam regulating valve is gradually opened, and the rotating speed of the steam-driven main water-feeding pump gradually rises until the rotating speed of the steam-driven main water-feeding pump reaches the minimum rotating speed requirement. And when the starting valve reaches a full-closed position, the steam-driven main water supply system of the nuclear power station is started. After that, the starting valve is kept closed completely, the starting control subsystem quits the rotation speed control, and the rotation speed control is realized by a steam regulating valve.
When the subsequent steam-driven main water-feeding pump is subjected to speed-up and loading, the electric converter receives a 4-20 mA given rotating speed signal and linearly converts the signal into a 0.2-1.0 Bar air signal to be sent to the mechanical speed regulator, a flyweight structure is designed in the mechanical speed regulator and used for detecting the actual rotating speed of the steam-driven main water-feeding pump, the mechanical speed regulator outputs torque to adjust the opening of the leakage-guiding valve according to the deviation between the given rotating speed signal and the actual rotating speed signal, the signal oil pressure is controlled, and the new steam valve opening is controlled by the signal oil pressure to adjust the steam inlet amount, so that the rotating speed control of the steam-driven water-.
The on-load speed regulation subsystem of the electrical converter (EP) and the mechanical speed regulator has a complex structure and has the problems of poor regulation precision, slow response, difficult debugging, multiple fault points, difficult fault elimination, poor human-computer interaction friendliness and the like.
Disclosure of Invention
In order to solve the technical problems, the invention provides a system and a method for controlling the rotating speed of a steam-driven main water-feeding pump of a nuclear power station, which can improve the precision of the rotating speed regulation of the steam-driven main water-feeding pump and optimize the reliability of the rotating speed control system.
The invention provides a rotation speed control system of a steam-driven main feed water pump of a nuclear power station, which comprises: the device comprises a digital controller, a protection trip circuit, a driver, an actuator and two rotating speed sensors;
the two rotation speed sensors are used for respectively acquiring the rotation speed of the steam-driven main water feeding pump, generating corresponding rotation speed pulse signals and transmitting the rotation speed pulse signals to the digital controller;
the digital controller is used for determining an actually measured rotating speed value of the steam-driven main water feeding pump according to two rotating speed pulse signals corresponding to the two rotating speed sensors, generating a corresponding control signal according to the actually measured rotating speed value and a given rotating speed signal, and transmitting the control signal to the driver;
and the driver is used for generating corresponding driving current according to the control signal and the feedback signal of the actuator, outputting the driving current to the actuator, driving the actuator to act so as to adjust the valve opening of the steam regulating valve, and adjusting the rotating speed of the steam-driven main feed water pump by adjusting the valve opening of the steam regulating valve.
Preferably, the digital controller is further configured to determine whether the two speed sensors have a fault according to the two speed pulse signals and the power consumption of the two speed sensors, and when one of the two speed sensors has a fault, the digital controller controls the alarm module to send out a fault alarm; when the two rotation speed sensors are in fault, the trip protection of the steam main feed water pump is triggered through the trip protection circuit.
Preferably, the digital controller is further configured to send trip instructions through two sets of channels when both the two rotation speed sensors fail; wherein each group of channels comprises two channels;
the protection trip circuit comprises two trip judging loops which are respectively electrically connected with the two groups of channels; each trip judgment loop is used for outputting a trip instruction to a protection system when two channels in a group of channels correspondingly connected with the trip judgment loop output the trip instruction, and the protection system discharges protection oil in a steam main water supply system of the nuclear power station to realize trip protection of the steam main water supply pump.
Preferably, a redundant power supply circuit is also included;
the redundant power supply circuit is electrically connected with the digital controller, the driver and the protection tripping circuit, and is used for receiving alternating current output by the alternating current power supply and direct current output by the direct current power supply and converting the received alternating current and the received direct current into direct current with a specified voltage grade to supply power to the rotating speed control system.
Preferably, the redundant power supply circuit includes: the device comprises a filter, a surge protector, a DC/DC converter, an AC/DC converter and a redundancy module;
the input end of the filter is connected with a direct current power supply, the output end of the filter is connected with the input end of the DC/DC converter, and the output end of the DC/DC converter is connected with the redundancy module;
the input end of the surge protector is connected with an alternating current power supply, the output end of the surge protector is connected with the input end of the AC/DC converter, and the output end of the AC/DC converter is connected with the redundancy module;
the redundancy module comprises two diodes, anodes of the two diodes are respectively connected with the output end of the DC/DC converter and the output end of the AC/DC converter, and cathodes of the two diodes are connected to be used as the output end of the redundancy power supply circuit.
Preferably, the digital controller comprises two isolation units, two rotating speed fault diagnosis units, two rotating speed calculation units and a PID control unit;
each isolation unit is electrically connected with one rotating speed sensor and one rotating speed calculation unit respectively, and is used for converting a high-grade rotating speed pulse signal output by the rotating speed sensor into a low-grade rotating speed pulse signal to be output to the rotating speed calculation unit and electrically isolating the low-grade rotating speed pulse signal from the high-grade rotating speed pulse signal;
the rotating speed calculating unit is electrically connected with the rotating speed fault diagnosis unit and is used for calculating an actual measurement rotating speed value of the steam-driven main water feeding pump according to the low-level rotating speed pulse signal and transmitting the low-level rotating speed pulse signal and the actual measurement rotating speed value of the steam-driven main water feeding pump to the rotating speed fault diagnosis unit;
the rotating speed fault diagnosis unit is used for judging whether the rotating speed sensor has a fault according to the actually measured rotating speed value of the steam-driven main water feeding pump and the power consumption condition of the rotating speed sensor, and if not, transmitting the low-level rotating speed pulse signal to the PID control unit;
and the PID control unit takes a high selection result of two actual measurement rotating speed values of the steam-driven main water feeding pump corresponding to the two rotating speed sensors and a given rotating speed signal as input, calculates the deviation between the given rotating speed value corresponding to the given rotating speed signal and the actual measurement rotating speed value, generates a corresponding control signal after the deviation between the given rotating speed value and the actual measurement rotating speed value is calculated by a PID algorithm, and sends the control signal to the driver.
Preferably, the system also comprises an information recording module;
the information recording module is in communication connection with the digital controller and is used for receiving the given rotating speed signal, the actual rotating speed signal, the driving signal and the alarm information from the digital controller and circularly recording the given rotating speed signal, the actual rotating speed signal, the driving signal and the alarm information.
The invention also provides a method for controlling the rotating speed of the steam-driven main feed water pump of the nuclear power station, which comprises the following steps:
respectively acquiring the rotating speed of the steam-driven main water feeding pump through two rotating speed sensors, generating corresponding rotating speed pulse signals, and transmitting the rotating speed pulse signals to a digital controller;
the digital controller determines an actually measured rotating speed value of the steam-driven main water feeding pump according to rotating speed pulse signals corresponding to the two rotating speed sensors, generates a corresponding control signal according to the actually measured rotating speed value and a given rotating speed signal, and transmits the control signal to the driver;
the driver generates corresponding driving current according to the control signal and the feedback signal of the actuator, outputs the driving current to the actuator to drive the actuator to act, adjusts the valve opening of the steam regulating valve through the actuator, and adjusts the rotating speed of the steam-driven main feed water pump through adjusting the valve opening of the steam regulating valve.
Preferably, the method further comprises the following steps:
and the digital controller judges whether the two rotating speed sensors break down or not according to the two rotating speed pulse signals and the power consumption conditions of the two rotating speed sensors, controls an alarm module to send out fault alarm when one rotating speed sensor breaks down, and triggers the trip protection of the steam-driven main feed water pump through the trip protection circuit when the two rotating speed sensors break down.
Preferably, the trip protection of the steam-driven main feed water pump is triggered through the trip protection circuit, and the trip protection method specifically comprises the following steps:
when the two rotating speed sensors are in fault, the digital controller respectively sends out tripping instructions through the two groups of channels; wherein each group of channels comprises two channels;
when two channels in the first group of channels of the first trip judgment loop in the protection trip circuit output trip instructions, the trip instructions are output to the protection system, or when two channels in the second group of channels of the second trip judgment loop in the protection trip circuit output trip instructions, the trip instructions are output to the protection system, and protection oil in the steam main water supply system of the nuclear power station is discharged through the protection system, so that the trip protection of the steam main water supply pump is realized.
The implementation of the invention has the following beneficial effects: the invention collects the rotating speed of the steam-driven main water-feeding pump through actual measurement, and adjusts the valve opening of the steam regulating valve according to the rotating speed of the steam-driven main water-feeding pump, the given rotating speed and the feedback signal of the actuator, thereby realizing the actual measurement and adjustment of the rotating speed of the steam-driven main water-feeding pump, improving the precision of the rotating speed adjustment of the steam-driven main water-feeding pump, and optimizing the reliability of the rotating speed control system of the steam-driven main water-feeding pump of the nuclear power station. In addition, the invention can fully automatically adjust the valve opening of the steam adjusting valve and improve the speed of adjusting the rotating speed of the steam main water feeding pump.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
Fig. 1 is a schematic block diagram of a steam-driven main supply system of a nuclear power station in the background art.
FIG. 2 is a schematic block diagram of a system for controlling the rotational speed of a steam-driven main feed water pump of a nuclear power plant according to the present invention.
Fig. 3 is a schematic diagram of interaction among a digital controller, a driver and an actuator provided by the invention.
Fig. 4 is a functional block diagram of a redundant power supply circuit provided by the present invention.
Fig. 5 is a logic diagram of the operation of the protection trip circuit provided by the present invention.
Fig. 6 is a functional block diagram of a digital controller provided by the present invention.
Detailed Description
The invention provides a speed control system of a steam-driven main feed water pump 4 of a nuclear power station, as shown in figure 2, the speed control system comprises: digital controller 1, protection trip circuit 8, driver 2, actuator 3 and two speed sensors 5.
The two rotation speed sensors 5 are used for respectively acquiring the rotation speed of the steam-driven main water feeding pump 4, generating corresponding rotation speed pulse signals and transmitting the rotation speed pulse signals to the digital controller 1.
The digital controller 1 is configured to determine an actual measurement rotation speed value of the steam-driven main feed water pump 4 according to two rotation speed pulse signals corresponding to the two rotation speed sensors 5, generate a corresponding control signal according to the actual measurement rotation speed value and a given rotation speed signal sent by an upstream system, and transmit the control signal to the driver 2.
The driver 2 is used for generating corresponding driving current according to the control signal and the feedback signal of the actuator 3, outputting the driving current to the actuator 3, driving the actuator 3 to act, adjusting the valve opening degree of the steam adjusting valve 6 through the actuator 3, and adjusting the rotating speed of the steam main feed water pump 4 through adjusting the valve opening degree of the steam adjusting valve 6. The feedback signal of the actuator 3 is a signal of the current valve opening of the steam control valve 6.
Here, the steam regulating valve 6 may be any one of the extraction valves or the new steam valve in fig. 1. The execution logic how the actuator 3 selects any one of the steam extraction valves in the steam regulating valve 6 or the valve opening of the new steam valve to regulate belongs to the prior art in the field, and is not described herein again.
As shown in fig. 3, the digital controller 1 includes a PID output unit 17 for outputting a control signal and a feedback receiving unit 10 for receiving a feedback signal, and the actuator 3 includes a command receiving unit 31 for receiving a driving current from the driver 2 and a state feedback unit 32 for outputting a feedback signal.
Further, the digital controller 1 is further configured to determine whether the two rotation speed sensors 5 have a fault according to the two rotation speed pulse signals and the power consumption conditions of the two rotation speed sensors, and when one rotation speed sensor 5 has a fault, the digital controller 1 controls the alarm module 10 to send out a fault alarm, and when both rotation speed sensors 5 have a fault, the trip protection of the steam-driven main water-feeding pump 4 is triggered through the trip protection circuit 8. The protective trip circuit 8 takes account of the risks of both a malfunction and a malfunction.
Further, the rotating speed control system of the steam-driven main feed water pump 4 of the nuclear power station also comprises a redundant power supply circuit 7.
The redundant power supply circuit 7 is electrically connected with the digital controller 1, the driver 2 and the protection tripping circuit, and is used for receiving alternating current of an alternating current power supply and direct current output by a direct current power supply, converting the received alternating current and the received direct current into direct current with a specified voltage grade, and supplying the direct current with the specified voltage grade to the rotating speed control system. Generally, the dc power of the predetermined voltage level is 24V dc power.
As shown in fig. 4, the redundant power supply circuit 7 includes: a filter 71, a surge protector 72, a DC/DC converter (DC-DC converter) 73, an AC/DC converter (AC-DC converter) 74, and a redundancy module 75.
The input end of the filter 71 is connected with a direct current power supply, the output end of the filter 71 is connected with the input end of the DC/DC converter 73, and the output end of the DC/DC converter 73 is connected with the redundancy module 75.
The input end of the surge protector 72 is connected to an alternating current power supply, the output end is connected to the input end of the AC/DC converter 74, and the output end of the AC/DC converter 74 is connected to the redundancy module 75.
The redundancy module 75 comprises two diodes, the anodes of which are connected to the output of the DC/DC converter 73 and the output of the AC/DC converter 74, respectively, and the cathodes of which are connected as the output of the redundancy power supply circuit 7. The input of the DC/DC converter 73 and the input of the AC/DC converter 74 may be directly connected. As described above, when the potential of the direct current output from the DC/DC converter 73 is higher, the direct current output from the output terminal of the DC/DC converter 73 is output, and when the potential of the direct current output from the AC/DC converter 74 is higher, the direct current output from the output terminal of the AC/DC converter 74 is output.
The redundant power supply circuit 7 fully considers redundancy and fault tolerance and has high reliability.
Further, the digital controller 1 is also used for sending tripping instructions through two groups of channels when the two rotation speed sensors 5 are in fault; wherein each group of channels comprises two channels. As shown in fig. 5, the first channel and the second channel on the digital controller 1 are grouped, and the third channel and the fourth channel are grouped.
The trip protection circuit 8 includes two trip judgment loops, such as a first trip judgment loop and a second trip judgment loop shown in fig. 5, and the two trip judgment loops are electrically connected to the two sets of channels respectively; each trip judgment loop is used for outputting a trip instruction to the protection system when two channels in the group of channels correspondingly connected with the trip judgment loop output the trip instruction, and the protection oil in the steam main water supply system of the nuclear power plant is discharged through the protection system, so that the trip protection of the steam main water supply pump 4 is realized.
Each trip judging loop can be two relays, input contacts of the two relays are respectively connected with two channels in the same group of channels, and output contacts of the two relays are connected to be used as output ends of the trip judging loops. When the digital controller 1 detects that any relay is in fault, the alarm module 10 is controlled to give an alarm.
The digital controller 1 sends out a tripping instruction through two groups of channels, and the protection tripping circuit 8 outputs the tripping instruction through two tripping judgment loops, so that redundancy and fault tolerance can be fully considered, and the reliability is high.
As shown in fig. 6, the digital controller 1 includes two isolation units 11, two rotational speed failure diagnosis units 12, two rotational speed calculation units 13, and a PID control unit 14.
Each isolation unit 11 is electrically connected to one of the rotation speed sensors 5 and one of the rotation speed calculation units 13, and is configured to convert a high-level rotation speed pulse signal (e.g., a rotation speed pulse signal having a voltage between 0V and 24V) output by the rotation speed sensor 5 into a low-level rotation speed pulse signal (e.g., a rotation speed pulse signal having a voltage of one of 5V, 3V, and 1.5V), output the low-level rotation speed pulse signal to the rotation speed calculation unit 13, and electrically isolate the low-level rotation speed pulse signal from the high-level rotation speed pulse signal.
The rotating speed calculating unit 13 is electrically connected to the rotating speed fault diagnosing unit 12, and is configured to calculate an actual measured rotating speed value of the steam-driven main feed water pump 4 according to the low-level rotating speed pulse signal, and transmit the low-level rotating speed pulse signal and the actual measured rotating speed value of the steam-driven main feed water pump to the rotating speed fault diagnosing unit 12.
The rotating speed fault diagnosis unit 12 is configured to determine whether the rotating speed sensor 5 is faulty according to the actually measured rotating speed value of the main steam feed water pump 4 and the power consumption condition of the rotating speed sensor, and if not, transmit a low-level rotating speed pulse signal to the PID control unit 14.
The PID control unit 14 takes the high selection result of the two measured rotating speed values of the main steam feed water pump 4 corresponding to the two rotating speed sensors 5 and the given rotating speed signal as input, calculates the deviation between the given rotating speed value corresponding to the given rotating speed signal and the measured rotating speed value, generates a corresponding control signal after the deviation between the given rotating speed value and the measured rotating speed value is calculated by a PID algorithm (controlled according to the proportion of the deviation), and sends the control signal to the driver 2.
The digital controller 1 also contains a fault management unit 15, an alarm and pump trip management unit 16.
The fault management unit 15 is electrically connected with the two rotating speed fault diagnosis units 12, each rotating speed fault diagnosis unit 12 respectively transmits a fault judgment result of the corresponding rotating speed sensor 5 to the fault management unit 15, the fault management unit 15 is used for judging whether one rotating speed sensor 5 is in fault or two rotating speed sensors 5 are in fault, if one rotating speed sensor 5 is in fault, the alarm module 10 is controlled to alarm through the alarm and pump tripping management unit 16, and when the two rotating speed sensors 5 are in fault, the alarm and pump tripping management unit 16 is used for controlling and protecting the tripping circuit 8 to trigger the tripping protection of the steam-driven main water feeding pump 4.
Further, the rotation speed control system of the steam-driven main feed water pump 4 of the nuclear power plant also comprises an information recording module 9.
The information recording module 9 is in communication connection with the digital controller 1, and is configured to receive the given rotation speed signal, the actual rotation speed signal, the driving signal, and the alarm information from the digital controller 1, perform loop recording on the given rotation speed signal, the actual rotation speed signal, the driving signal, and the alarm information, and analyze the cause of the fault. Here, the alarm information includes trip protection information of the steam-driven main water-feeding pump 4, and comprehensive alarm information that at least two rotation speed sensors 5 and at least two rotation speed sensors 5 are failed.
Preferably, the digital controller 1 controls the alarm module 10 to give an alarm when the given rotating speed signal is not received, and controls the main steam feed water pump 4 to maintain the current rotating speed. The digital controller 1 is also connected with an air conditioner of the whole system, and controls the alarm module 10 to alarm when the air conditioner of the system fails. When the digital controller 1 crashes, the control protection system reduces the oil pressure of the signal oil to zero to perform trip protection, when one path of power supply in the redundant power supply circuit 7 is abnormal, the control alarm module 10 gives an alarm, and when two paths of power supply in the redundant power supply circuit 7 are abnormal, the control protection system performs trip protection.
The invention also provides a method for controlling the rotating speed of the steam-driven main feed water pump 4 of the nuclear power station, which comprises the following steps:
the method comprises the following steps that the rotating speeds of a steam-driven main water feeding pump 4 are respectively collected through two rotating speed sensors 5, corresponding rotating speed pulse signals are generated, and the rotating speed pulse signals are transmitted to a digital controller 1;
the digital controller 1 determines an actual measurement rotating speed value of the steam main water feeding pump 4 according to rotating speed pulse signals corresponding to the two rotating speed sensors 5, generates a corresponding control signal according to the actual measurement rotating speed value and a given rotating speed signal, and transmits the control signal to the driver 2;
the driver 2 generates corresponding driving current according to the control signal and the feedback signal of the actuator, outputs the driving current to the actuator 3, drives the actuator 3 to act, adjusts the valve opening of the steam adjusting valve 6 through the actuator 3, and adjusts the rotating speed of the steam main feed water pump 4 through adjusting the valve opening of the steam adjusting valve.
Further, the method for controlling the rotating speed of the steam-driven main feed water pump 4 of the nuclear power plant further comprises the following steps:
the digital controller 1 judges whether the two rotation speed sensors 5 are in failure or not according to the two rotation speed pulse signals and the power consumption conditions of the two rotation speed sensors 5, when one rotation speed sensor 5 is in failure, the digital controller 1 controls the alarm module 10 to give out failure alarm, and when the two rotation speed sensors 5 are in failure, the trip protection of the steam-driven main water-feeding pump 4 is triggered through the protection trip circuit 8.
Further, the trip protection of the steam main water supply pump 4 is triggered by protecting the trip circuit 8, and the method specifically comprises the following steps:
when the two rotating speed sensors 5 are in fault, the digital controller 1 respectively sends out tripping instructions through the two groups of channels; wherein each group of channels comprises two channels;
when the first trip judgment loop in the trip protection circuit 8 outputs a trip instruction on two channels in the first group of channels, the trip instruction is output to the protection system, or when the second trip judgment loop in the trip protection circuit 8 outputs a trip instruction on two channels in the second group of channels, the trip instruction is output to the protection system, and the protection oil in the steam main water supply system of the nuclear power station is discharged through the protection system, so that the trip protection of the steam main water supply pump 4 is realized.
In summary, the invention collects the rotation speed of the steam-driven main water-feeding pump 4 through two rotation speed sensors 5, outputs two corresponding rotation speed pulse signals, the digital controller 1 determines the actual measurement rotation speed value of the steam-driven main water-feeding pump 4 according to the two rotation speed pulse signals, generates a corresponding control signal according to the actual measurement rotation speed value and the given rotation speed signal, controls the driver 2 to generate a corresponding driving current through the control signal and the feedback signal of the actuator, drives the actuator to act through the driving current, and adjusts the valve opening of the steam regulating valve 6 through the actuator 3, thereby realizing the adjustment of the rotation speed of the steam-driven main water-feeding pump 4.
According to the invention, the rotating speed of the steam-driven main water-feeding pump 4 is acquired in real time, the steam-driven main water-feeding pump 4 is regulated in real time according to the rotating speed of the steam-driven main water-feeding pump 4 and the given rotating speed, and the rotating speed of the steam-driven main water-feeding pump 4 is comprehensively regulated according to the feedback signal of the actuator 3, so that the response speed and the regulation precision of the rotating speed can be improved when the rotating speed of the steam-driven main water-feeding pump 4 is regulated, and the difficulty of regulating the rotating speed of the steam-driven main water-feeding pump 4 is.
Further, the digital controller 1 also records the given rotation speed signal, the actual rotation speed signal, the driving signal and the alarm information into the information recording module 9, so that a user can conveniently analyze, solve problems and debug according to the information. The digital controller 1 can also give an alarm for different problems encountered in the rotating speed control system, so that a user can conveniently monitor and troubleshoot the problems in the rotating speed control system, and the problem that the on-load speed regulation subsystem is difficult to troubleshoot is solved.
The digital controller 1 can also be correspondingly configured with a human-computer interaction interface (such as a display), so that a user can conveniently input a rated rotating speed value, a minimum rotating speed value and a parameter value of a PID algorithm of the steam main feed water pump 4 to the digital controller 1 through the human-computer interaction interface, the digital controller 1 participates in adjusting the rotating speed of the steam main feed water pump 4 according to the parameters input by the user, and the digital controller has good human-computer interaction performance. The user can also monitor the operation parameters of the rotating speed control system through a human-computer interaction interface and can perform interventional treatment.
Moreover, an interface for function expansion can be reserved on the digital controller 1, so that the function expansibility is improved.
The invention can ensure the stable water supply of the secondary loop of the nuclear power station, ensure the continuity and the reliability of the operation of the nuclear power station and improve the economic benefit of the nuclear power station.
The foregoing is a more detailed description of the invention in connection with specific preferred embodiments and it is not intended that the invention be limited to these specific details. For those skilled in the art to which the invention pertains, several simple deductions or substitutions can be made without departing from the spirit of the invention, and all shall be considered as belonging to the protection scope of the invention.
Claims (8)
1. A rotational speed control system of a steam-driven main feed water pump of a nuclear power station is characterized by comprising: the device comprises a digital controller, a protection trip circuit, a driver, an actuator and two rotating speed sensors;
the two rotation speed sensors are used for respectively acquiring the rotation speed of the steam-driven main water feeding pump, generating corresponding rotation speed pulse signals and transmitting the rotation speed pulse signals to the digital controller;
the digital controller is used for determining an actually measured rotating speed value of the steam-driven main water feeding pump according to two rotating speed pulse signals corresponding to the two rotating speed sensors, generating a corresponding control signal according to the actually measured rotating speed value and a given rotating speed signal, and transmitting the control signal to the driver;
the driver is used for generating corresponding driving current according to the control signal and the feedback signal of the actuator, outputting the driving current to the actuator, driving the actuator to act so as to adjust the valve opening of the steam regulating valve, and adjusting the rotating speed of the steam-driven main feed water pump by adjusting the valve opening of the steam regulating valve;
the digital controller is further used for judging whether the two rotating speed sensors have faults or not according to the two rotating speed pulse signals and the power consumption conditions of the two rotating speed sensors, and when one rotating speed sensor has a fault, the digital controller controls the alarm module to send out fault alarm; when the two rotation speed sensors are in fault, the trip protection of the steam main feed water pump is triggered through the trip protection circuit.
2. The system for controlling the rotation speed of the steam-driven main feed water pump of the nuclear power plant as recited in claim 1,
the digital controller is also used for respectively sending out tripping instructions through the two groups of channels when the two rotating speed sensors are in failure; wherein each group of channels comprises two channels;
the protection trip circuit comprises two trip judging loops which are respectively electrically connected with the two groups of channels; each trip judgment loop is used for outputting a trip instruction to a protection system when two channels in a group of channels correspondingly connected with the trip judgment loop output the trip instruction, and the protection system discharges protection oil in a steam main water supply system of the nuclear power station to realize trip protection of the steam main water supply pump.
3. The system for controlling the rotation speed of the steam-driven main feed water pump of the nuclear power plant as recited in claim 1, further comprising a redundant power supply circuit;
the redundant power supply circuit is electrically connected with the digital controller, the driver and the protection tripping circuit, and is used for receiving alternating current output by the alternating current power supply and direct current output by the direct current power supply and converting the received alternating current and the received direct current into direct current with a specified voltage grade to supply power to the rotating speed control system.
4. A system for controlling the speed of a steam-operated main feed water pump of a nuclear power plant as claimed in claim 3, wherein the redundant power supply circuit comprises: the device comprises a filter, a surge protector, a DC/DC converter, an AC/DC converter and a redundancy module;
the input end of the filter is connected with a direct current power supply, the output end of the filter is connected with the input end of the DC/DC converter, and the output end of the DC/DC converter is connected with the redundancy module;
the input end of the surge protector is connected with an alternating current power supply, the output end of the surge protector is connected with the input end of the AC/DC converter, and the output end of the AC/DC converter is connected with the redundancy module;
the redundancy module comprises two diodes, anodes of the two diodes are respectively connected with the output end of the DC/DC converter and the output end of the AC/DC converter, and cathodes of the two diodes are connected to be used as the output end of the redundancy power supply circuit.
5. The rotational speed control system of the steam-driven main feed water pump of the nuclear power plant as claimed in claim 1, wherein the digital controller comprises two isolation units, two rotational speed fault diagnosis units, two rotational speed calculation units and a PID control unit;
each isolation unit is electrically connected with one rotating speed sensor and one rotating speed calculation unit respectively, and is used for converting a high-grade rotating speed pulse signal output by the rotating speed sensor into a low-grade rotating speed pulse signal to be output to the rotating speed calculation unit and electrically isolating the low-grade rotating speed pulse signal from the high-grade rotating speed pulse signal;
the rotating speed calculating unit is electrically connected with the rotating speed fault diagnosis unit and is used for calculating an actual measurement rotating speed value of the steam-driven main water feeding pump according to the low-level rotating speed pulse signal and transmitting the low-level rotating speed pulse signal and the actual measurement rotating speed value of the steam-driven main water feeding pump to the rotating speed fault diagnosis unit;
the rotating speed fault diagnosis unit is used for judging whether the rotating speed sensor has a fault according to the actually measured rotating speed value of the steam-driven main water feeding pump and the power consumption condition of the rotating speed sensor, and if not, transmitting the low-level rotating speed pulse signal to the PID control unit;
and the PID control unit takes a high selection result of two actual measurement rotating speed values of the steam-driven main water feeding pump corresponding to the two rotating speed sensors and a given rotating speed signal as input, calculates the deviation between the given rotating speed value corresponding to the given rotating speed signal and the actual measurement rotating speed value, generates a corresponding control signal after the deviation between the given rotating speed value and the actual measurement rotating speed value is calculated by a PID algorithm, and sends the control signal to the driver.
6. The system for controlling the rotating speed of the steam-driven main feed water pump of the nuclear power plant as claimed in claim 5, characterized by further comprising an information recording module;
the information recording module is in communication connection with the digital controller and is used for receiving the given rotating speed signal, the actual rotating speed signal, the driving signal and the alarm information from the digital controller and circularly recording the given rotating speed signal, the actual rotating speed signal, the driving signal and the alarm information.
7. A method for controlling the rotating speed of a steam-driven main feed water pump of a nuclear power station is characterized by comprising the following steps:
respectively acquiring the rotating speed of the steam-driven main water feeding pump through two rotating speed sensors, generating corresponding rotating speed pulse signals, and transmitting the rotating speed pulse signals to a digital controller;
the digital controller determines an actually measured rotating speed value of the steam-driven main water feeding pump according to rotating speed pulse signals corresponding to the two rotating speed sensors, generates a corresponding control signal according to the actually measured rotating speed value and a given rotating speed signal, and transmits the control signal to the driver;
the driver generates corresponding driving current according to the control signal and a feedback signal of the actuator, outputs the driving current to the actuator, drives the actuator to act, adjusts the valve opening of the steam regulating valve through the actuator, and adjusts the rotating speed of the steam-driven main feed water pump through adjusting the valve opening of the steam regulating valve;
wherein, still include the following step:
and the digital controller judges whether the two rotating speed sensors break down or not according to the two rotating speed pulse signals and the power consumption conditions of the two rotating speed sensors, controls an alarm module to send out fault alarm when one rotating speed sensor breaks down, and triggers the trip protection of the steam-driven main water feeding pump through a protection trip circuit when the two rotating speed sensors break down.
8. The method for controlling the rotating speed of the steam-driven main water-feeding pump of the nuclear power plant as claimed in claim 7, wherein the trip protection of the steam-driven main water-feeding pump is triggered through the protection trip circuit, and the method comprises the following steps:
when the two rotating speed sensors are in fault, the digital controller respectively sends out tripping instructions through the two groups of channels; wherein each group of channels comprises two channels;
when two channels in the first group of channels of the first trip judgment loop in the protection trip circuit output trip instructions, the trip instructions are output to the protection system, or when two channels in the second group of channels of the second trip judgment loop in the protection trip circuit output trip instructions, the trip instructions are output to the protection system, and protection oil in the steam main water supply system of the nuclear power station is discharged through the protection system, so that the trip protection of the steam main water supply pump is realized.
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| CN111794934B (en) * | 2020-08-13 | 2024-04-30 | 刘亚辉 | Method for changing pneumatic feed pump system into full-frequency-conversion electric feed pump system and brand-new logic control system thereof |
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