CN116994787B - Method and system for controlling nuclear power of high-temperature gas cooled reactor nuclear power plant - Google Patents
Method and system for controlling nuclear power of high-temperature gas cooled reactor nuclear power plant Download PDFInfo
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- 238000000034 method Methods 0.000 title claims abstract description 42
- 230000008569 process Effects 0.000 claims abstract description 14
- 239000001307 helium Substances 0.000 claims description 137
- 229910052734 helium Inorganic materials 0.000 claims description 137
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 137
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 94
- 230000001276 controlling effect Effects 0.000 claims description 46
- 239000007789 gas Substances 0.000 claims description 27
- 230000008859 change Effects 0.000 claims description 24
- 230000006870 function Effects 0.000 claims description 20
- 238000012544 monitoring process Methods 0.000 claims description 19
- 230000001105 regulatory effect Effects 0.000 claims description 14
- 239000002826 coolant Substances 0.000 claims description 11
- 238000006243 chemical reaction Methods 0.000 claims description 8
- 238000004590 computer program Methods 0.000 claims description 8
- 230000002159 abnormal effect Effects 0.000 claims description 6
- 238000001816 cooling Methods 0.000 claims description 6
- 239000003758 nuclear fuel Substances 0.000 claims description 6
- 238000012423 maintenance Methods 0.000 claims description 4
- 230000005856 abnormality Effects 0.000 claims description 3
- 239000000498 cooling water Substances 0.000 claims description 3
- 230000004907 flux Effects 0.000 claims description 3
- 238000012545 processing Methods 0.000 claims description 3
- 230000009257 reactivity Effects 0.000 abstract description 6
- 230000008901 benefit Effects 0.000 description 3
- 238000003491 array Methods 0.000 description 2
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- 230000009295 sperm incapacitation Effects 0.000 description 2
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The invention belongs to the technical field of nuclear power, and particularly relates to a method and a system for controlling nuclear power of a high-temperature gas cooled reactor nuclear power plant. The invention discloses a method for controlling nuclear power of a high-temperature gas cooled reactor nuclear power plant, which comprises the following steps: the system state is monitored in real time, a nuclear power measured value and a nuclear power set value are obtained, the measured value and the set value are compared through a selection module, a proper control mode is selected, a switching process is executed, and a switching result is confirmed. The invention improves the accuracy and flexibility of nuclear power control, can accurately control the reactivity of a reactor in a wider power range, reduces the operation difficulty and risk caused by the complexity and instability of a nuclear power control system, improves the stability and reliability of the system, can automatically or manually exit an automatic control mode when the control system breaks down or alarms, and ensures the safe operation of a nuclear power plant by manually controlling related equipment by an operator, and reduces the large fluctuation of lifting and inserting a control rod.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to a method and a system for controlling the nuclear power of a high-temperature gas cooled reactor nuclear power plant.
Background
The reactor nuclear power control system of the current domestic high-temperature gas cooled reactor nuclear power plant is similar to a pressurized water reactor, the depth of a control rod in a reactor core is regulated by a control rod controller to control the reactor nuclear power, and meanwhile, the primary loop hot helium temperature and the cold helium temperature are used as regulating parameters of a secondary regulation controller. The three cascade controllers together form a cascade control system for the nuclear power of the reactor.
Because of the three-level control system of the coordination control system, the coupling ratio among all levels is more, and all control variables are mutually influenced, the control rod is easy to lift and insert and greatly fluctuates during test or operation. In addition, the control rods have insufficient reactivity control capability for the reactor in a large power range. In view of the foregoing, there is a need for improvements in reactor nuclear power control systems.
Disclosure of Invention
This section is intended to outline some aspects of embodiments of the application and to briefly introduce some preferred embodiments. Some simplifications or omissions may be made in this section as well as in the description of the application and in the title of the application, which may not be used to limit the scope of the application.
The present invention has been made in view of the above-described problems.
Therefore, the technical problems solved by the invention are as follows: how to improve the stability of the reactor nuclear power control system of the high-temperature gas cooled reactor nuclear power plant, and how to improve the large-scale control capacity of the reactor nuclear power control system, thereby realizing more efficient control of the reactor nuclear power control system.
In order to solve the technical problems, the invention provides the following technical scheme: a method for controlling nuclear power of a high-temperature gas cooled reactor nuclear power plant comprises the following steps: the system state is monitored in real time, a nuclear power measured value and a nuclear power set value are obtained, the measured value and the set value are compared through a selection module, a proper control mode is selected, a switching process is executed, and a switching result is confirmed.
As a preferable scheme of the method for controlling the nuclear power of the high-temperature gas cooled reactor nuclear power plant, the invention comprises the following steps: the real-time monitoring system state comprises the steps of collecting real-time reactor parameter data through a monitoring module of a nuclear power plant, wherein the data comprise the internal temperature of a reactor, the helium flow rate of a coolant, the position of a control rod, the neutron flux, the flow and the power of a main helium fan and the flow and the power of a main water supply pump;
Acquiring an operation target and state of a nuclear power plant through an automatic control module of the nuclear power plant, wherein the target and state comprise an expected power grid load, an expected reactor power level, an equipment maintenance plan of the nuclear power plant, meteorological conditions, a supply condition of a coolant, a burnup and replacement period of nuclear fuel and other environment and equipment parameters, and determining a nuclear power set value adapting to the current actual condition according to the target and state;
The control module has a complete fault detection and processing program, when detecting that the nuclear power plant is abnormal or has an alarm, such as overheating of a reactor, exhaustion of nuclear fuel, failure of a cooling system, incapacitation of a control rod, deviation of flow and power of a main helium blower or a main water supply pump from normal values, the system automatically or artificially exits from an automatic control mode, and operators directly control related equipment through a manual operator to ensure safe operation of the nuclear power plant.
As a preferable scheme of the method for controlling the nuclear power of the high-temperature gas cooled reactor nuclear power plant, the invention comprises the following steps: the selection of the proper control mode comprises the steps that when the deviation between the core power set value and the core power measured value is smaller than 5% of the core power, a deviation signal of the core power set value and the core power measured value is input to a control rod controller through a selection module, and the core power is regulated only through the control rod.
As a preferable scheme of the method for controlling the nuclear power of the high-temperature gas cooled reactor nuclear power plant, the invention comprises the following steps: when the deviation between the nuclear power set value and the nuclear power measured value is greater than 5% of the nuclear power, the nuclear power set value is input to a main helium fan rotating speed setter through a selection module, and the nuclear power is regulated by controlling the main helium fan and a main water supply pump based on a corresponding relation function of the nuclear power and the main helium fan flow;
the corresponding relation function of the nuclear power and the flow of the main helium fan is expressed as:
Where P core is the nuclear power, ρ is the helium density, Q is the primary helium fan flow, P circ is the primary helium fan power, η is the primary helium fan efficiency.
As a preferable scheme of the method for controlling the nuclear power of the high-temperature gas cooled reactor nuclear power plant, the invention comprises the following steps: the switching process comprises the steps of inputting a control signal obtained by a main helium fan rotating speed setter into a main helium fan controller, controlling a main helium fan frequency converter, controlling the rotating speed of the main helium fan, changing the temperature of a reactor core, and introducing reactive change in the change of the temperature of the reactor core so as to regulate the power of the reactor.
As a preferable scheme of the method for controlling the nuclear power of the high-temperature gas cooled reactor nuclear power plant, the invention comprises the following steps: the switching process comprises the steps that the output of the main helium fan is input to a main water supply pump flow matcher of the main helium fan, a main water supply pump rotating speed control signal is obtained through a corresponding relation function of the main helium fan flow and the main water supply pump flow, then a signal for controlling the opening of an electric main water supply pump frequency converter and a pneumatic pump valve is output through a main water supply pump rotating speed controller, the main water supply pump rotating speed is further controlled, the main water supply pump rotating speed is changed, the main water supply flow is controlled, the output heat power of an evaporator is further changed, the temperature of cold and hot helium is further changed, the temperature of a reactor core is indirectly changed, and the temperature of the reactor core is changed to introduce reactive change, so that the power of the reactor is further adjusted;
the corresponding relation function of the main helium fan flow and the main water supply pump flow is expressed as:
Wherein Q w is the main feedwater pump flow, c p is the specific heat capacity of the water, deltaT is the temperature rise of the water in the steam generator, and ε is the thermal efficiency of the steam generator.
As a preferable scheme of the method for controlling the nuclear power of the high-temperature gas cooled reactor nuclear power plant, the invention comprises the following steps: the switching process comprises a control rod controller, a main helium fan rotating speed controller and a main water supply pump rotating speed controller which are respectively connected with a DCS soft manual controller, and the DCS soft manual controller is used as an emergency control means when automatic control fails or a system alarms, when the emergency control is in an emergency condition, the automatic control is automatically or manually withdrawn, and an operator directly controls related equipment through the manual controller so as to ensure safe operation of the high-temperature gas cooled reactor nuclear power plant, and the manual control link is rigorously designed and can rapidly and effectively cope with possible abnormal conditions.
Another object of the present invention is to provide a nuclear power control system for a high temperature gas cooled reactor nuclear power plant, which can solve the problems of instability and complexity of nuclear power control by monitoring the system status in real time, comparing the measured value with the set value, and selecting an appropriate control mode.
In order to solve the technical problems, the invention provides the following technical scheme: the nuclear power control system of the high-temperature gas cooled reactor nuclear power plant comprises a real-time monitoring module, a selection module, a main helium fan rotating speed setter, a main helium fan rotating speed controller, a main helium fan, a main water supply pump flow matcher of the main helium fan, a main water supply pump rotating speed controller, a main water supply pump, an evaporator, a control rod controller, a control rod manual operator, a main helium fan manual operator, a main water supply pump manual operator and a control rod;
The real-time monitoring module is used for acquiring a nuclear power measured value and a nuclear power set value, monitoring and collecting reactor parameter data, and automatically detecting and processing fault conditions;
The selection module is used for comparing the measured value with the set value and selecting a proper nuclear power control mode according to the deviation;
the control rod controller is used for receiving the signal of the selection module and controlling the nuclear power of the reactor according to the signal, and mainly plays a role when the deviation between the set value of the nuclear power and the measured value of the nuclear power is less than 5% of the nuclear power;
the main helium fan rotating speed setter is used for receiving a signal of the selection module when the deviation between the nuclear power set value and the nuclear power measured value is greater than 5% of the nuclear power, and converting the set nuclear power into a rotating speed control signal of the main helium fan;
the main helium fan rotating speed controller is used for receiving a control signal of the main helium fan rotating speed setter and then controlling the main helium fan frequency converter to adjust the rotating speed of the main helium fan;
the main helium fan is used for providing cooling helium flow, and the rotating speed of the main helium fan is controlled by the rotating speed controller of the main helium fan;
the main water supply pump flow matcher of the main helium fan is used for receiving the output of the main helium fan and obtaining a main water supply pump rotating speed control signal according to a corresponding relation function of the main helium fan flow and the main water supply pump flow;
The main water feed pump rotating speed controller is used for receiving signals of a main water feed pump flow matcher of the main helium fan and then controlling the rotating speed of the main water feed pump;
the main water feed pump is used for providing the flow of the coolant, and the rotating speed of the main water feed pump is controlled by the rotating speed controller of the main water feed pump;
The evaporator is used for converting cooling water from a water supply pump into steam, and the output heat power of the evaporator can influence the temperature of cold and hot helium and the power of a reactor;
The control rod is used for regulating and controlling nuclear reaction and controlling nuclear power;
The manual operators are connected to the controllers and are used for controlling related equipment through the manual operators manually when abnormality or alarm occurs to the system.
A computer device comprising a memory and a processor, said memory storing a computer program, characterized in that said processor, when executing said computer program, performs the steps of a method for controlling the nuclear power of a high temperature gas cooled reactor nuclear power plant.
A computer readable storage medium having stored thereon a computer program, characterized in that the computer program when executed by a processor performs the steps of a method for nuclear power control of a high temperature gas cooled reactor nuclear power plant.
The invention has the beneficial effects that: the invention improves the accuracy and flexibility of nuclear power control, can accurately control the reactivity of a reactor in a wider power range, reduces the operation difficulty and risk caused by the complexity and instability of a nuclear power control system, improves the stability and reliability of the system, can automatically or manually exit an automatic control mode when the control system breaks down or alarms, ensures the safe operation of a nuclear power plant by manually controlling related equipment by an operator, reduces the large fluctuation of lifting and inserting a control rod, and enhances the stability and safety of operation.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings that are needed in the description of the embodiments will be briefly described below, it being obvious that the drawings in the following description are only some embodiments of the present invention, and that other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art. Wherein:
FIG. 1 is a flow chart of a method for controlling nuclear power of a high temperature gas cooled reactor nuclear power plant according to an embodiment of the present invention;
FIG. 2 is a block diagram of a nuclear power control system of a high temperature gas cooled reactor nuclear power plant according to an embodiment of the present invention;
Detailed Description
So that the manner in which the above recited objects, features and advantages of the present invention can be understood in detail, a more particular description of the invention, briefly summarized above, may be had by reference to the embodiments, some of which are illustrated in the appended drawings. All other embodiments, which can be made by one of ordinary skill in the art based on the embodiments of the present invention without making any inventive effort, shall fall within the scope of the present invention.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention, but the present invention may be practiced in other ways other than those described herein, and persons skilled in the art will readily appreciate that the present invention is not limited to the specific embodiments disclosed below.
Further, reference herein to "one embodiment" or "an embodiment" means that a particular feature, structure, or characteristic can be included in at least one implementation of the invention. The appearances of the phrase "in one embodiment" in various places in the specification are not necessarily all referring to the same embodiment, nor are separate or alternative embodiments mutually exclusive of other embodiments.
While the embodiments of the present invention have been illustrated and described in detail in the drawings, the cross-sectional view of the device structure is not to scale in the general sense for ease of illustration, and the drawings are merely exemplary and should not be construed as limiting the scope of the invention. In addition, the three-dimensional dimensions of length, width and depth should be included in actual fabrication.
Also in the description of the present invention, it should be noted that the orientation or positional relationship indicated by the terms "upper, lower, inner and outer", etc. are based on the orientation or positional relationship shown in the drawings, are merely for convenience of describing the present invention and simplifying the description, and do not indicate or imply that the apparatus or elements referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus should not be construed as limiting the present invention. Furthermore, the terms "first, second, or third" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
The terms "mounted, connected, and coupled" should be construed broadly in this disclosure unless otherwise specifically indicated and defined, such as: can be fixed connection, detachable connection or integral connection; it may also be a mechanical connection, an electrical connection, or a direct connection, or may be indirectly connected through an intermediate medium, or may be a communication between two elements. The specific meaning of the above terms in the present invention will be understood in specific cases by those of ordinary skill in the art.
Example 1
Referring to fig. 1, in one embodiment of the present invention, a method for controlling nuclear power of a high temperature gas cooled reactor nuclear power plant is provided, including:
Monitoring the system state in real time to obtain a nuclear power measured value and a nuclear power set value;
comparing the measured value with a set value through a selection module, and selecting a proper control mode;
and executing a switching process and confirming a switching result.
S1: monitoring the system state in real time to obtain a nuclear power measured value and a nuclear power set value;
Further, the real-time monitoring system state comprises the steps of collecting real-time reactor parameter data through a monitoring module of the nuclear power plant, wherein the data comprise the internal temperature of the reactor, the flow rate of coolant helium, the position of a control rod, neutron flux, the flow and power of a main helium fan and the flow and power of a main water supply pump;
Acquiring an operation target and state of a nuclear power plant through an automatic control module of the nuclear power plant, wherein the target and state comprise an expected power grid load, an expected reactor power level, an equipment maintenance plan of the nuclear power plant, meteorological conditions, a supply condition of a coolant, a burnup and replacement period of nuclear fuel and other environment and equipment parameters, and determining a nuclear power set value adapting to the current actual condition according to the target and state;
The control module has a complete fault detection and processing program, when detecting that the nuclear power plant is abnormal or has an alarm, such as overheating of a reactor, exhaustion of nuclear fuel, failure of a cooling system, incapacitation of a control rod, deviation of flow and power of a main helium blower or a main water supply pump from normal values, the system automatically or artificially exits from an automatic control mode, and operators directly control related equipment through a manual operator to ensure safe operation of the nuclear power plant.
It should be noted that, on the one hand, the core power measurement value may obtain a deviation signal from the core power set point, as a negative feedback link of the control rod controller. On the other hand, the core power measured value is also used for comparing with the core power set value, namely, when the deviation between the set core power value and the current core power is smaller, the core power is regulated only through the control rod, and the control loop is provided with a negative feedback link and is closed-loop control; when the deviation is large, the nuclear power set value is directly controlled in an open loop mode, and the nuclear power is regulated through the main helium blower and the main water supply pump.
S2: comparing the measured value with a set value through a selection module, and selecting a proper control mode;
further, the selecting a proper control mode includes inputting a deviation signal of the core power set value and the core power measured value to the control rod controller through the selecting module when the deviation of the core power set value and the core power measured value is less than 5% of the core power, and adjusting the core power only through the control rod.
It should be noted that, on the one hand, when the range of the power change requirement is smaller, the reactivity provided by the control rod can better control the nuclear power of the reactor, on the other hand, because the deviation signal is smaller, the action amplitude of the control rod does not excessively fluctuate for the control rod, so that the excessive nuclear power change rate is not caused, the steady-state error can be eliminated by closed-loop control, and the control performance is more excellent.
It should be noted that, in the present invention, the threshold of 5% is set empirically and practically, mainly considering the following aspects:
Stability: in the nuclear reaction process, in order to maintain the stability of the reaction, it is necessary to ensure the accuracy of power control. If the threshold is too large, such as 10%, when the deviation of the actual power from the set power exceeds the threshold, unstable reaction process may be caused, and the running risk of the system may be increased. If the threshold is too small, such as 1%, the control mode may be frequently switched, which may also increase the instability of the system.
Efficiency is that: when the power deviation is within 5%, the speed of the nuclear reaction is adjusted by adjusting the position of the control rod, which is a more direct and effective control manner, and the set power level can be reached quickly and accurately. When the power deviation exceeds 5%, the temperature and the power of the reactor are indirectly controlled by adjusting the rotation speed of the main helium blower and the main water supply pump, which is a milder and safer way, but the efficiency is slightly lower than that of directly adjusting the control rod.
Safety: safe operation of a nuclear reactor is a primary consideration. The setting of the threshold requires trade-offs of accuracy, efficiency and safety. The threshold of 5% can ensure the safety of the system while ensuring the accuracy and efficiency.
Further, selecting a proper control mode further comprises inputting the nuclear power set value to the main helium fan rotating speed setter through the selection module when the deviation between the nuclear power set value and the nuclear power measured value is greater than 5% of the nuclear power, and adjusting the nuclear power by controlling the main helium fan and the main water supply pump based on the corresponding relation function of the nuclear power and the main helium fan flow;
It should be noted that, on the one hand, when the range of the power change requirement is large, the control rod cannot provide good control performance, so that the control is selected by the main helium fan through the selection module, on the other hand, because the deviation signal is relatively large, the power density of the high-temperature gas cooled reactor is relatively small, the heat capacity of the reactor is relatively large, the power change speed of the reactor is not fast, and the nuclear power is not required to be fast and reach high control precision in a short time, so that the open loop control mode is suitable.
The corresponding relation function of the nuclear power and the flow of the main helium fan is expressed as:
Where P core is the nuclear power, ρ is the helium density, Q is the primary helium fan flow, P circ is the primary helium fan power, η is the primary helium fan efficiency.
It should be noted that, the "corresponding relation function between the core power and the flow of the main helium fan" is obtained through debugging data during the debugging period of the unit, the change rate of the rotating speed of the main helium fan is limited through the "main helium fan controller", and after the rotating speed rate is limited, the excessive flow change of a loop is not caused, namely, the excessive change of the temperature of the reactor core is not caused, the excessive reactivity is not introduced, so that the excessive change rate of the core power is not caused, and meanwhile, the open loop control mode is selected, the excessive fluctuation of the output of the controller is not caused, and the excessive change rate of the core power is not caused.
S3: and executing a switching process and confirming a switching result.
Furthermore, the switching process comprises inputting a control signal obtained by the main helium fan rotating speed setter into the main helium fan controller, controlling the main helium fan frequency converter, controlling the main helium fan rotating speed, changing the reactor core temperature, and introducing reactive change to the reactor core temperature change so as to adjust the reactor power.
Furthermore, the switching process also comprises the steps that the output of the main helium fan is input to a main water supply pump flow matcher of the main helium fan, a main water supply pump rotating speed control signal is obtained through a corresponding relation function of the main helium fan flow and the main water supply pump flow, then a signal for controlling the opening of an electric main water supply pump frequency converter and a pneumatic pump regulating valve is output through a main water supply pump rotating speed controller, the main water supply pump rotating speed is controlled, the main water supply pump rotating speed is changed, the main water supply flow is controlled, the output thermal power of an evaporator is further changed, the temperature of cold and hot helium is changed, the temperature of a reactor core is indirectly changed, and the reactor core temperature is changed to introduce reactive change, so that the reactor power is regulated;
It should be noted that, the main helium fan rotating speed is linked with the main water supply flow rotating speed control, so as to make the flows of the first loop and the second loop mutually matched, the corresponding relation function of the main helium fan and the main water supply pump is obtained through debugging data during the debugging period of the unit, the change rate of the main water supply pump rotating speed is limited through a main water supply pump rotating speed controller, after the rotating speed rate is limited, the excessive flow change of the second loop is not caused, namely the excessive change of the heat transfer of the evaporator is not caused, the excessive change of the helium cold and hot temperature is not caused, the excessive change of the core temperature is not caused, the excessive reactivity is not introduced, the excessive nuclear power change rate is not caused, and meanwhile, the open loop control mode is selected, the excessive fluctuation of the output of the controller is not caused, and the excessive nuclear power change rate is not caused.
The corresponding relation function of the main helium fan flow and the main water supply pump flow is expressed as:
Wherein Q w is the main feedwater pump flow, c p is the specific heat capacity of the water, deltaT is the temperature rise of the water in the steam generator, and ε is the thermal efficiency of the steam generator.
Furthermore, the switching process also comprises a control rod controller, a main helium fan rotating speed controller and a main water supply pump rotating speed controller which are respectively connected with a DCS soft manual operator, and the DCS soft manual operator is used as an emergency control means when automatic control fails or a system alarms, when the emergency control means is in an emergency condition, the automatic control is automatically or manually withdrawn, and an operator directly controls related equipment through the manual operator so as to ensure safe operation of the high-temperature gas cooled reactor nuclear power plant, and the manual control link is strictly designed and can rapidly and effectively cope with possible abnormal conditions.
Example 2
A second embodiment of the invention, which differs from the previous embodiment, is:
The functions, if implemented in the form of software functional units and sold or used as a stand-alone product, may be stored in a computer-readable storage medium. Based on this understanding, the technical solution of the present invention may be embodied essentially or in a part contributing to the prior art or in a part of the technical solution, in the form of a software product stored in a storage medium, comprising several instructions for causing a computer device (which may be a personal computer, a server, a network device, etc.) to perform all or part of the steps of the method according to the embodiments of the present invention. And the aforementioned storage medium includes: a usb disk, a removable hard disk, a Read-only memory (ROM), a random access memory (RAM, random Access Memory), a magnetic disk, or an optical disk, or other various media capable of storing program codes.
Logic and/or steps represented in the flowcharts or otherwise described herein, e.g., a ordered listing of executable instructions for implementing logical functions, can be embodied in any computer-readable medium for use by or in connection with an instruction execution system, apparatus, or device, such as a computer-based system, processor-containing system, or other system that can fetch the instructions from the instruction execution system, apparatus, or device and execute the instructions. For the purposes of this description, a "computer-readable medium" can be any means that can contain, store, communicate, propagate, or transport the program for use by or in connection with the instruction execution system, apparatus, or device.
More specific examples (a non-exhaustive list) of the computer-readable medium would include the following: an electrical connection (electronic device) having one or more wires, a portable computer diskette (magnetic device), a Random Access Memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber device, and a portable compact disc read-only memory (CDROM). In addition, the computer readable medium may even be paper or other suitable medium on which the program is printed, as the program may be electronically captured, via, for instance, optical scanning of the paper or other medium, then compiled, interpreted or otherwise processed in a suitable manner, if necessary, and then stored in a computer memory.
It is to be understood that portions of the present invention may be implemented in hardware, software, firmware, or a combination thereof. In the above-described embodiments, the various steps or methods may be implemented in software or firmware stored in a memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, may be implemented using any one or combination of the following techniques, as is well known in the art: discrete logic circuits having logic gates for implementing logic functions on data signals, application specific integrated circuits having suitable combinational logic gates, programmable Gate Arrays (PGAs), field Programmable Gate Arrays (FPGAs), and the like.
Example 3
Referring to fig. 2, a third embodiment of the present invention provides a method system for controlling nuclear power of a high temperature gas cooled reactor nuclear power plant, which includes a real-time monitoring module, a selection module, a main helium fan rotation speed setting device, a main helium fan rotation speed controller, a main helium fan, a main water supply pump flow matcher of the main helium fan, a main water supply pump rotation speed controller, a main water supply pump, an evaporator, a control rod controller, a control rod manual operator, a main helium fan manual operator, a main water supply pump manual operator, and a control rod;
The real-time monitoring module is used for acquiring a nuclear power measured value and a nuclear power set value, monitoring and collecting reactor parameter data, and automatically detecting and processing fault conditions;
The selection module is used for comparing the measured value with the set value and selecting a proper nuclear power control mode according to the deviation;
the control rod controller is used for receiving the signal of the selection module and controlling the nuclear power of the reactor according to the signal, and mainly plays a role when the deviation between the set value of the nuclear power and the measured value of the nuclear power is less than 5% of the nuclear power;
the main helium fan rotating speed setter is used for receiving a signal of the selection module when the deviation between the nuclear power set value and the nuclear power measured value is greater than 5% of the nuclear power, and converting the set nuclear power into a rotating speed control signal of the main helium fan;
the main helium fan rotating speed controller is used for receiving a control signal of the main helium fan rotating speed setter and then controlling the main helium fan frequency converter to adjust the rotating speed of the main helium fan;
the main helium fan is used for providing cooling helium flow, and the rotating speed of the main helium fan is controlled by the rotating speed controller of the main helium fan;
the main water supply pump flow matcher of the main helium fan is used for receiving the output of the main helium fan and obtaining a main water supply pump rotating speed control signal according to a corresponding relation function of the main helium fan flow and the main water supply pump flow;
The main water feed pump rotating speed controller is used for receiving signals of a main water feed pump flow matcher of the main helium fan and then controlling the rotating speed of the main water feed pump;
the main water feed pump is used for providing the flow of the coolant, and the rotating speed of the main water feed pump is controlled by the rotating speed controller of the main water feed pump;
The evaporator is used for converting cooling water from a water supply pump into steam, and the output heat power of the evaporator can influence the temperature of cold and hot helium and the power of a reactor;
The control rod is used for regulating and controlling nuclear reaction and controlling nuclear power;
The manual operators are connected to the controllers and are used for controlling related equipment through the manual operators manually when abnormality or alarm occurs to the system.
Example 4
In order to verify the beneficial effects of the invention, scientific demonstration is carried out through economic benefit calculation.
And (3) performing nuclear power control by adopting a traditional method (A) and a method (B) according to the invention respectively in two identical high-temperature gas cooled reactor nuclear power plants.
TABLE 1
As can be seen from the above table, the performance of the nuclear power plant employing the present invention in power control is significantly improved compared to the conventional method of the nuclear power plant: the adjustment times of the insertion depth of the control rod of the nuclear power plant B are reduced by 70%, the temperature deviation of the reactor core and the helium flow speed deviation of the coolant are reduced, and the power consumption of the main helium fan is reduced by 10%.
The daily power consumption was (2000 kW-1800 kW) 24 hours=4800 kwh, and the electricity cost was 480 yuan/day. The electricity fee saving of one year can reach 480 yuan/day, 365 days=175,200 yuan.
In addition, as the adjustment times of the control rod are reduced, the abrasion of the control rod is also reduced, thereby prolonging the service life of the control rod and reducing the maintenance cost and the shutdown loss caused by failure. Meanwhile, the reduced reactor core temperature deviation and the coolant helium flow speed deviation can enable the nuclear reaction to be more stable, and the safety of the nuclear power plant is enhanced.
In conclusion, the invention can ensure the safe and stable operation of the nuclear power plant and realize the great improvement of economic benefit.
It should be noted that the above embodiments are only for illustrating the technical solution of the present invention and not for limiting the same, and although the present invention has been described in detail with reference to the preferred embodiments, it should be understood by those skilled in the art that modifications and equivalents may be made thereto without departing from the spirit and scope of the technical solution of the present invention, which is intended to be covered by the scope of the claims of the present invention.
Claims (5)
1. A method for controlling nuclear power of a high temperature gas cooled reactor nuclear power plant, comprising:
Monitoring the system state in real time to obtain a nuclear power measured value and a nuclear power set value;
comparing the measured value with a set value through a selection module, and selecting a proper control mode;
executing a switching process and confirming a switching result;
the real-time monitoring system state comprises the steps of collecting real-time reactor parameter data through a monitoring module of a nuclear power plant, wherein the data comprise the internal temperature of a reactor, the helium flow rate of a coolant, the position of a control rod, the neutron flux, the flow and the power of a main helium fan and the flow and the power of a main water supply pump;
Acquiring an operation target and state of a nuclear power plant through an automatic control module of the nuclear power plant, wherein the target and state comprise an expected power grid load, an expected reactor power level, an equipment maintenance plan of the nuclear power plant, meteorological conditions, a supply condition of a coolant, a burnup and replacement period of nuclear fuel and other environment and equipment parameters, and determining a nuclear power set value adapting to the current actual condition according to the target and state;
When abnormal operation or alarm of the nuclear power plant is detected, the reactor is overheated, nuclear fuel is exhausted, a cooling system fails, a control rod cannot work normally, the flow and the power of a main helium blower or a main water supply pump deviate from normal values, the system automatically or artificially exits from an automatic control mode, and operators directly control related equipment through a manual operator to ensure safe operation of the nuclear power plant;
When the deviation between the core power set value and the core power measured value is less than 5% of the core power, the deviation signal between the core power set value and the core power measured value is input to a control rod controller through a selection module, and the core power is regulated only through the control rod;
The method for selecting the proper control mode further comprises the steps that when the deviation between a nuclear power set value and a nuclear power measured value is greater than 5% of the nuclear power, the nuclear power set value is input to a main helium fan rotating speed setter through a selection module, and the nuclear power is regulated by controlling the main helium fan and a main water supply pump based on a corresponding relation function of the nuclear power and the main helium fan flow;
the corresponding relation function of the nuclear power and the flow of the main helium fan is expressed as:
Wherein P core is the nuclear power, ρ is the helium density, Q is the primary helium fan flow, P circ is the primary helium fan power, η is the primary helium fan efficiency;
the switching process also comprises the steps of inputting a control signal obtained by the main helium fan rotating speed setter into a main helium fan controller, controlling a main helium fan frequency converter, controlling the rotating speed of the main helium fan, changing the temperature of a reactor core, changing the temperature of the reactor core, introducing reactive change, and further adjusting the power of the reactor;
The switching process also comprises the steps that the output of the main helium fan is input to a main water supply pump flow matcher of the main helium fan, a main water supply pump rotating speed control signal is obtained through a corresponding relation function of the main helium fan flow and the main water supply pump flow, then a signal for controlling the opening of an electric main water supply pump frequency converter and a pneumatic pump regulating valve is output through a main water supply pump rotating speed controller, the main water supply pump rotating speed is further controlled, the main water supply pump rotating speed is changed, the main water supply flow is controlled, the output heat power of an evaporator is further changed, the temperature of cold and hot helium is further changed, the temperature of a reactor core is indirectly changed, and the reactor core temperature is changed to introduce reactive change, so that the power of a reactor is further adjusted;
the corresponding relation function of the main helium fan flow and the main water supply pump flow is expressed as:
Where Q w is the main feedwater pump flow, c p is the specific heat capacity of the water, deltaT is the temperature rise of the water in the steam generator, and ε is the thermal efficiency of the steam generator.
2. The method for controlling the nuclear power of a high-temperature gas cooled reactor nuclear power plant according to claim 1, wherein: the switching process also comprises a control rod controller, a main helium fan rotating speed controller and a main water supply pump rotating speed controller which are respectively connected with a DCS soft manual controller, and the DCS soft manual controller is used as an emergency control means when automatic control fails or a system alarms, when the emergency control is in an emergency condition, the automatic control is automatically or manually withdrawn, and an operator directly controls related equipment through the manual controller so as to ensure safe operation of the high-temperature gas cooled reactor nuclear power plant, and the manual control link is strictly designed and can rapidly and effectively cope with possible abnormal conditions.
3. A system employing a method of nuclear power control of a high temperature gas cooled reactor nuclear power plant as claimed in any one of claims 1 to 2, wherein: the device comprises a real-time monitoring module, a selection module, a main helium fan rotating speed setter, a main helium fan rotating speed controller, a main helium fan, a main water supply pump flow matcher of the main helium fan, a main water supply pump rotating speed controller, a main water supply pump, an evaporator, a control rod controller, a control rod manual operator, a main helium fan manual operator, a main water supply pump manual operator and a control rod;
The real-time monitoring module is used for acquiring a nuclear power measured value and a nuclear power set value, monitoring and collecting reactor parameter data, and automatically detecting and processing fault conditions;
The selection module is used for comparing the measured value with the set value and selecting a proper nuclear power control mode according to the deviation;
the control rod controller is used for receiving the signal of the selection module and controlling the nuclear power of the reactor according to the signal, and mainly plays a role when the deviation between the set value of the nuclear power and the measured value of the nuclear power is less than 5% of the nuclear power;
the main helium fan rotating speed setter is used for receiving a signal of the selection module when the deviation between the nuclear power set value and the nuclear power measured value is greater than 5% of the nuclear power, and converting the set nuclear power into a rotating speed control signal of the main helium fan;
the main helium fan rotating speed controller is used for receiving a control signal of the main helium fan rotating speed setter and then controlling the main helium fan frequency converter to adjust the rotating speed of the main helium fan;
the main helium fan is used for providing cooling helium flow, and the rotating speed of the main helium fan is controlled by the rotating speed controller of the main helium fan;
the main water supply pump flow matcher of the main helium fan is used for receiving the output of the main helium fan and obtaining a main water supply pump rotating speed control signal according to a corresponding relation function of the main helium fan flow and the main water supply pump flow;
The main water feed pump rotating speed controller is used for receiving signals of a main water feed pump flow matcher of the main helium fan and then controlling the rotating speed of the main water feed pump;
the main water feed pump is used for providing the flow of the coolant, and the rotating speed of the main water feed pump is controlled by the rotating speed controller of the main water feed pump;
The evaporator is used for converting cooling water from a water supply pump into steam, and the output heat power of the evaporator can influence the temperature of cold and hot helium and the power of a reactor;
The control rod is used for regulating and controlling nuclear reaction and controlling nuclear power;
The manual operators are connected to the controllers and are used for controlling related equipment through the manual operators manually when abnormality or alarm occurs to the system.
4. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any one of claims 1 to 2 when the computer program is executed.
5. A computer-readable storage medium having stored thereon a computer program, characterized by: the computer program implementing the steps of the method of any one of claims 1 to 2 when executed by a processor.
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