CN116610031A - Nuclear power unit coordination control system and method with incremental state observer - Google Patents
Nuclear power unit coordination control system and method with incremental state observer Download PDFInfo
- Publication number
- CN116610031A CN116610031A CN202310557355.XA CN202310557355A CN116610031A CN 116610031 A CN116610031 A CN 116610031A CN 202310557355 A CN202310557355 A CN 202310557355A CN 116610031 A CN116610031 A CN 116610031A
- Authority
- CN
- China
- Prior art keywords
- module
- deviation
- value
- output end
- input end
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000000034 method Methods 0.000 title claims abstract description 23
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 78
- 238000012937 correction Methods 0.000 claims abstract description 54
- 230000005032 impulse control Effects 0.000 claims abstract description 8
- 239000002826 coolant Substances 0.000 claims description 75
- 238000005259 measurement Methods 0.000 claims description 44
- 230000008569 process Effects 0.000 claims description 8
- 230000001276 controlling effect Effects 0.000 claims description 6
- 230000004069 differentiation Effects 0.000 claims description 5
- 230000010354 integration Effects 0.000 claims description 5
- 230000001105 regulatory effect Effects 0.000 claims description 3
- 230000009471 action Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000010355 oscillation Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G05—CONTROLLING; REGULATING
- G05B—CONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
- G05B13/00—Adaptive control systems, i.e. systems automatically adjusting themselves to have a performance which is optimum according to some preassigned criterion
- G05B13/02—Adaptive control systems, i.e. systems automatically adjusting themselves to have a performance which is optimum according to some preassigned criterion electric
- G05B13/04—Adaptive control systems, i.e. systems automatically adjusting themselves to have a performance which is optimum according to some preassigned criterion electric involving the use of models or simulators
- G05B13/042—Adaptive control systems, i.e. systems automatically adjusting themselves to have a performance which is optimum according to some preassigned criterion electric involving the use of models or simulators in which a parameter or coefficient is automatically adjusted to optimise the performance
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Health & Medical Sciences (AREA)
- Artificial Intelligence (AREA)
- Computer Vision & Pattern Recognition (AREA)
- Evolutionary Computation (AREA)
- Medical Informatics (AREA)
- Software Systems (AREA)
- Physics & Mathematics (AREA)
- General Physics & Mathematics (AREA)
- Automation & Control Theory (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a nuclear power unit coordination control system with an incremental state observer and a method thereof, wherein double impulse control is carried out according to a water supply flow correction value used for PID regulation of the water supply flow and a unit load correction value used for PID regulation of the unit load, and then the unit load is controlled according to the result of the double impulse control; the system and the method can meet the functional requirements of peak regulation and frequency modulation of the load of the tracking power grid of the reactor.
Description
Technical Field
The invention belongs to the field of nuclear science and engineering, and relates to a nuclear power unit coordination control system with an incremental state observer and a method thereof.
Background
The coordination control system of the nuclear power unit takes the whole nuclear power unit as a whole for control, adopts a hierarchical control system structure, organically combines the functions of automatic regulation, logic control, interlocking protection and the like, and forms a comprehensive control system with multiple control functions and meeting the control requirements under different operation modes and different working conditions. The nuclear power unit coordination control system based on the modern control theory is the current development direction. The coordination control system of the nuclear power unit is a complex large system with multiple inputs and multiple outputs, and a close coupling relation exists between each control quantity and the regulated quantity. The control variable is under the combined action of the internal structural attribute and the external operation condition of the equipment, the control characteristic is nonlinear, and the control variable has the distribution parameter and time-varying characteristic, so that the accurate control is difficult to realize at present. The cascade control system adopted at present has the advantage of being capable of reducing the maximum deviation and integral error of the control variable, but the dynamic regulation performance is still to be improved when the unit runs under variable working conditions, and the control scheme does not meet the functional requirement of peak regulation and frequency modulation of the reactor tracking power grid load.
Disclosure of Invention
The invention aims to overcome the defects of the prior art, and provides a nuclear power unit coordination control system with an incremental state observer and a nuclear power unit coordination control method, which can meet the functional requirements of peak regulation and frequency modulation of a reactor tracking power grid load.
In order to achieve the above purpose, the nuclear power unit coordination control method with the incremental state observer provided by the invention comprises the following steps:
acquiring a water supply flow correction value for PID (proportion integration differentiation) regulation of the water supply flow; acquiring a unit load correction value for unit load PID adjustment; acquiring a loop coolant flow correction value for loop coolant flow PID regulation; acquiring a power correction value for PID adjustment of reactor power;
performing double impulse control according to the water supply flow correction value for PID regulation of the water supply flow and the unit load correction value for PID regulation of the unit load, and then controlling the unit load according to the result of the double impulse control;
and performing three-impulse control according to the unit load correction value for unit load PID regulation, the power correction value for reactor power PID regulation and the primary loop coolant flow correction value for primary loop coolant flow PID regulation, and then controlling the reactor power according to the result of the three-impulse control.
The specific process for obtaining the water supply flow correction value for PID regulation of the water supply flow is as follows:
obtaining a water supply flow measurement value, calculating a water supply flow calculation value according to the unit load measurement value, and performing deviation calculation on the water supply flow calculation value and the water supply flow measurement value to obtain a water supply flow first deviation value; and adjusting the first deviation value of the water supply flow through an increment calculator and an inertia link, performing deviation calculation on the first deviation value of the water supply flow and a water supply flow set value obtained after fitting the water supply flow with a history operation database to obtain a second deviation value of the water supply flow, correcting the increment calculator by using the second deviation value of the water supply flow to obtain a first correction value, enabling the second deviation value of the water supply flow to be equal to zero, and finally taking the first correction value as a water supply flow correction value for PID adjustment of the water supply flow.
The specific process for obtaining the unit load correction value for unit load PID regulation comprises the following steps:
obtaining a unit load measured value, performing deviation calculation on a unit load set value and the unit load measured value to obtain a unit load first deviation value, performing deviation calculation on the unit load calculated value and the unit load measured value to obtain a unit load second deviation value, performing weighted calculation on the unit load first deviation value and the unit load second deviation value, and obtaining a unit load corrected value for PID adjustment of the unit load.
The specific process of obtaining the primary loop coolant flow correction value for primary loop coolant flow PID regulation is as follows:
obtaining a loop coolant flow measurement value, calculating a loop coolant flow calculation value according to the reactor power measurement value, and performing deviation calculation on the loop coolant flow calculation value and the loop coolant flow measurement value to obtain a loop coolant flow first deviation value; and regulating the first deviation value of the flow of the loop coolant through an incremental calculator and an inertia link, performing deviation calculation on the first deviation value and a loop coolant flow set value obtained after fitting the first deviation value and the history operation database to obtain a second deviation value of the flow of the loop coolant, correcting the incremental calculator by using the second deviation value of the flow of the loop coolant to obtain a second correction value, enabling the second deviation value of the flow of the loop coolant to be equal to zero, and finally using the second correction value as a loop coolant flow correction value for PID regulation of the flow of the loop coolant.
The specific process for obtaining the power correction value for the PID adjustment of the reactor power is as follows:
and obtaining a reactor power measurement value, performing deviation calculation on the reactor power set value and the reactor power measurement value to obtain a reactor power deviation value, and calculating a power correction value for PID (proportion integration differentiation) adjustment of the reactor power according to the reactor power deviation value.
The nuclear power unit coordination control system with the incremental state observer comprises a first calculation module, a second calculation module, a third calculation module and a fourth calculation module, wherein the first calculation module, the second calculation module, the third calculation module and the fourth calculation module are sequentially connected.
The first calculation module comprises a water supply flow historical operation database module, a water supply flow measurement module, a water supply flow setting module, a first deviation module, a second deviation module, a first function solver, a first PID module, a first increment calculator, a second increment calculator, a first inertia link module and a second inertia link module;
the output end of the water supply flow history operation database module is communicated with the input end of the water supply flow setting module; the output end of the water supply flow setting module is communicated with the first input end of the first deviation module, and the output end of the first deviation module is communicated with the input end of the first increment calculator and the input end of the second increment calculator; the output end of the water supply flow measuring module is communicated with the first input end of the second deviation module, the output end of the second deviation module is communicated with the input end of the first increment calculator, the output end of the first increment calculator is communicated with the input end of the first inertia link module, the output end of the first inertia link module is communicated with the input end of the second increment calculator, the output end of the second increment calculator is communicated with the input end of the second inertia link module, the output end of the second inertia link module is communicated with the second input end of the first deviation module and the input end of the first PID module, the output end of the first PID module is communicated with the first input end of the first T module, the second input end of the second deviation module is communicated with the output end of the first function solver, and the input end of the first function solver is communicated with the first output end of the unit load measuring module.
The second calculation module comprises a third deviation module, a fourth deviation module, a second function solver, a summation calculator, a first T module, a unit load measurement module, a unit load setting module and a unit load manual/automatic main control module;
the second output end of the unit load measuring module and the first output end of the unit load setting module are communicated with the input end of the third deviation module, the second output end of the unit load setting module is communicated with the first input end of the fourth deviation module, the output end of the third deviation module and the output end of the fourth deviation module are communicated with the input end of the summation calculator, the output end of the summation calculator is communicated with the second input end of the first T module, the output end of the first T module is communicated with the input end of the unit load manual/automatic main control module, the output end of the unit load manual/automatic main control module is communicated with the first input end of the second T module, the input end of the second function solver is communicated with the first output end of the power setting module, and the output end of the second function solver is communicated with the second input end of the fourth deviation module.
The third calculation module comprises a fifth deviation module, a second PID module, a second T module, a power setting module, a power measuring module and a reactor power manual/automatic main control module;
the second output end of the power setting module and the first output end of the power measuring module are communicated with the input end of a fifth deviation module, the output end of the fifth deviation module is communicated with the input end of a second PID module, the output end of the second PID module is communicated with the second input end of a second T module, the output end of the second T module is communicated with the input end of a reactor power manual/automatic main control module, and the third input end of the second T module is communicated with the output end of a third PID module.
The fourth calculation module comprises a sixth deviation module, a seventh deviation module, a third function solver, a third PID module, a third increment calculator, a fourth increment calculator, a third inertia link module, a fourth inertia link module, a loop coolant flow measurement module, a loop coolant flow historical operation database module and a loop coolant flow setting module;
the input end of the third function solver is communicated with the second output end of the power measuring module, the output end of the third function solver is communicated with the first input end of the fourth deviation module, the output end of the first loop coolant flow measuring module and the output end of the first loop coolant flow measuring module are communicated with the input end of the sixth deviation module, the output end of the sixth deviation module is communicated with the first input end of the third increment calculator, the output end of the third increment calculator is communicated with the input end of the third inertia link module, the output end of the third inertia link module is communicated with the input end of the fourth increment calculator, the output end of the fourth increment calculator is communicated with the input end of the fourth inertia link module, the first output end of the fourth inertia link module is communicated with the input end of the third PID module, the output end of the seventh deviation module is communicated with the first input end of the seventh deviation module, the output end of the seventh deviation module is respectively communicated with the second input end of the third increment calculator and the second output end of the fourth increment calculator, the output end of the fourth increment calculator is communicated with the first coolant flow setting module, and the output end of the fourth inertia link module is communicated with the first output end of the fourth flow setting module.
The invention has the following beneficial effects:
when the nuclear power unit coordination control method and system with the incremental state observer are specifically operated, the incremental state observer is added to serve as feedforward of the control variable so as to predict the change trend of the control variable and correct the output of the control variable, so that the phenomena of power overshoot or oscillation caused by the output characteristic of the PID regulator of the main control loop of the reactor and the inertia of the reactor are effectively overcome, and the key effect on the stability of the reactor is achieved. The incremental function observer is based on a nonlinear controlled system, has control stability and accuracy for nonlinear distributed control variable disturbance, and particularly can track parameter changes in time when a unit is operated under variable working conditions, so that the robustness of a nuclear power unit control system is improved, a control thought is provided for a nuclear power unit to subsequently participate in power grid peak regulation and frequency modulation, and the demand of a reactor for tracking power grid load to carry out peak regulation and frequency modulation is met. In addition, the water supply flow incremental state observer and the loop coolant flow incremental state observer provided by the invention are provided with an inertia link adjusting loop, and the inertia link is provided with a negative feedback closed-loop characteristic, and the amplitude of the inertia link is reduced along with the increase of frequency, so that the inertia link has a low-pass filtering function.
Drawings
Fig. 1 is a schematic structural view of the present invention.
The system comprises a water supply flow history operation database module 1, a water supply flow measurement module 2, a water supply flow setting module 3, a first deviation module 4, a second deviation module 5, a third deviation module 6, a fourth deviation module 7, a fifth deviation module 8, a sixth deviation module 9, a seventh deviation module 10, a first function solver 11, a second function solver 12, a third function solver 13, a sum calculator 14, a first PID module 15, a second PID module 16, a third PID module 17, a first T module 18, a second T module 19, a first increment calculator 20, a second increment calculator 21, a third increment calculator 22, a fourth increment calculator 23, a first inertia module 24, a second inertia module 25, a third inertia module 26, a fourth inertia module 27, a unit load measurement module 28, a unit load setting module 29, a unit load setting module 30, a power loop module 31, a first power loop module 32, a first power loop module 33, a first main control module 34, a first manual flow calculation system and a first cooling agent flow calculation module 38, a first manual flow calculation system and/or a manual flow calculation system module 37, and a manual flow calculation system module.
Detailed Description
In order to make the present invention better understood by those skilled in the art, the following description will clearly and completely describe the technical solutions in the embodiments of the present invention with reference to the accompanying drawings, and it is apparent that the described embodiments are only some embodiments of the present invention, not all embodiments, but not intended to limit the scope of the present disclosure. In addition, in the following description, descriptions of well-known structures and techniques are omitted so as not to unnecessarily obscure the concepts of the present disclosure. All other embodiments, which can be made by those skilled 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 accompanying drawings, there is shown a schematic structural diagram in accordance with a disclosed embodiment of the invention. The figures are not drawn to scale, wherein certain details are exaggerated for clarity of presentation and may have been omitted. The shapes of the various regions, layers and their relative sizes, positional relationships shown in the drawings are merely exemplary, may in practice deviate due to manufacturing tolerances or technical limitations, and one skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions as actually required.
The nuclear power unit coordination control method with the incremental state observer comprises the following steps:
1) Obtaining a water supply flow measurement value, calculating a water supply flow calculation value according to the unit load measurement value, and performing deviation calculation on the water supply flow calculation value and the water supply flow measurement value to obtain a water supply flow first deviation value; adjusting the first deviation value of the water supply flow through an increment calculator and an inertia link, performing deviation calculation on the first deviation value of the water supply flow and a water supply flow set value obtained after fitting the water supply flow and the history operation database to obtain a second deviation value of the water supply flow, correcting the increment calculator by using the second deviation value of the water supply flow to obtain a first correction value, enabling the second deviation value of the water supply flow to be equal to zero, and finally taking the first correction value as a water supply flow correction value for PID adjustment of the water supply flow;
2) Obtaining a unit load measured value, performing deviation calculation on a unit load set value and the unit load measured value to obtain a unit load first deviation value, performing deviation calculation on the unit load calculated value and the unit load measured value to obtain a unit load second deviation value, performing weighted calculation on the unit load first deviation value and the unit load second deviation value, and obtaining a unit load corrected value for PID adjustment of the unit load;
3) Performing double impulse control according to the water supply flow correction value for PID regulation of the water supply flow and the unit load correction value for PID regulation of the unit load, and then controlling the unit load according to the result of the double impulse control;
4) Obtaining a loop coolant flow measurement value, calculating a loop coolant flow calculation value according to the reactor power measurement value, and performing deviation calculation on the loop coolant flow calculation value and the loop coolant flow measurement value to obtain a loop coolant flow first deviation value; adjusting the first deviation value of the coolant flow of the loop through an incremental calculator and an inertia link, performing deviation calculation on the first deviation value and a loop coolant flow set value obtained after fitting the first deviation value and the loop coolant flow set value through a history operation database to obtain a second deviation value of the coolant flow of the loop, correcting the incremental calculator through the second deviation value of the coolant flow of the loop to obtain a second correction value, enabling the second deviation value of the coolant flow of the loop to be equal to zero, and finally taking the second correction value as a loop coolant flow correction value for PID adjustment of the coolant flow of the loop;
5) Obtaining a reactor power measurement value, performing deviation calculation on a reactor power set value and the reactor power measurement value to obtain a reactor power deviation value, and calculating a power correction value for PID (proportion integration differentiation) adjustment of the reactor power according to the reactor power deviation value;
6) And performing three-impulse control according to the unit load correction value for unit load PID regulation, the power correction value for reactor power PID regulation and the primary loop coolant flow correction value for primary loop coolant flow PID regulation, and then controlling the reactor power according to the result of the three-impulse control.
Referring to fig. 1, the coordination control system of a nuclear power unit with an incremental state observer according to the present invention includes a first calculation module 37, a second calculation module 38, a third calculation module 39, and a fourth calculation module 40;
the first calculation module 37 comprises a water supply flow history operation database module 1, a water supply flow measurement module 2, a water supply flow setting module 3, a first deviation module 4, a second deviation module 5, a first function solver 11, a first PID module 15, a first increment calculator 20, a second increment calculator 21, a first inertia link module 24 and a second inertia link module 25, wherein the output end of the water supply flow history operation database module 1 is communicated with the input end of the water supply flow setting module 3; the output end of the water supply flow setting module 3 is communicated with the first input end of the first deviation module 4, and the output end of the first deviation module 4 is communicated with the input end of the first increment calculator 20 and the input end of the second increment calculator 21; the output end of the water flow measuring module 2 is communicated with the first input end of the second deviation module 5, the output end of the second deviation module 5 is communicated with the input end of the first increment calculator 20, the output end of the first increment calculator 20 is communicated with the input end of the first inertia element module 24, the output end of the first inertia element module 24 is communicated with the input end of the second increment calculator 21, the output end of the second increment calculator 21 is communicated with the input end of the second inertia element module 25, the output end of the second inertia element module 25 is communicated with the second input end of the first deviation module 4 and the input end of the first PID module 15, the output end of the first PID module 15 is communicated with the first input end of the first T module 18, the second input end of the second deviation module 5 is communicated with the output end of the first function solver 11, and the input end of the first function solver 11 is communicated with the first output end of the unit load measuring module 28.
The second calculation module 38 includes a third deviation module 6, a fourth deviation module 7, a second function solver 12, a summation calculator 14, a first T module 18, a unit load measurement module 28, a unit load setting module 29, and a unit load manual/automatic master control module 35, where a second output end of the unit load measurement module 28 and a first output end of the unit load setting module 29 are connected with an input end of the third deviation module 6, a second output end of the unit load setting module 29 is connected with a first input end of the fourth deviation module 7, an output end of the third deviation module 6 and an output end of the fourth deviation module 7 are connected with an input end of the summation calculator 14, an output end of the summation calculator 14 is connected with a second input end of the first T module 18, an output end of the first T module 18 is connected with an input end of the unit load manual/automatic master control module 35, an output end of the unit load manual/automatic master control module 35 is connected with a first input end of the second T module 19, an input end of the second function solver 12 is connected with an output end of the fourth function solver 12.
The third calculation module 39 includes a fifth deviation module 8, a second PID module 16, a second T module 19, a power setting module 30, a power measurement module 31, and a manual/automatic reactor power control module 36, where a second output end of the power setting module 30 and a first output end of the power measurement module 31 are connected to an input end of the fifth deviation module 8, an output end of the fifth deviation module 8 is connected to an input end of the second PID module 16, an output end of the second PID module 16 is connected to a second input end of the second T module 19, an output end of the second T module 19 is connected to an input end of the manual/automatic reactor power control module 36, and a third input end of the second T module 19 is connected to an output end of the third PID module 17.
The fourth calculation module 40 includes a sixth deviation module 9, a seventh deviation module 10, a third function solver 13, a third PID module 17, a third incremental calculator 22, a fourth incremental calculator 23, a third inertia link module 26, a fourth inertia link module 27, a first loop coolant flow measurement module 32, a first loop coolant flow history operation database module 33, and a first loop coolant flow setting module 34, where an input end of the third function solver 13 is connected to a second output end of the power measurement module 31, an output end of the third function solver 13 is connected to a first input end of the fourth deviation module 6, an output end of the first loop coolant flow measurement module 21 and an output end of the first loop coolant flow measurement module 32 are connected to a first input end of the third incremental calculator 22, an output end of the third incremental calculator 22 is connected to an input end of the third inertia link module 26, an output end of the third inertia link module 26 is connected to an output end of the fourth incremental calculator 23, an output end of the fourth loop calculator 23 is connected to an input end of the fourth incremental calculator module 27 is connected to an input end of the fourth incremental calculator 27, an output end of the fourth loop coolant flow measurement module 21 and an output end of the fourth loop coolant flow measurement module 32 is connected to an output end of the fourth incremental calculator 27, an output end of the fourth incremental calculator 22 is connected to an output end of the fourth incremental calculator 27, and an output end of the fourth incremental calculator 27 is connected to an output end of the fourth incremental calculator 27, and an output end of the fourth incremental calculator is connected to an output end of the fourth incremental calculator 27 is connected to an output end of the fourth incremental calculator 22 is connected to an output end of the fourth incremental calculator, an output of the one-circuit coolant flow setting module 34 communicates with a second input of the seventh deviation module 10.
Claims (10)
1. A coordination control method of a nuclear power unit with an incremental state observer is characterized by comprising the following steps:
acquiring a water supply flow correction value for PID (proportion integration differentiation) regulation of the water supply flow; acquiring a unit load correction value for unit load PID adjustment; acquiring a loop coolant flow correction value for loop coolant flow PID regulation; acquiring a power correction value for PID adjustment of reactor power;
performing double impulse control according to the water supply flow correction value for PID regulation of the water supply flow and the unit load correction value for PID regulation of the unit load, and then controlling the unit load according to the result of the double impulse control;
and performing three-impulse control according to the unit load correction value for unit load PID regulation, the power correction value for reactor power PID regulation and the primary loop coolant flow correction value for primary loop coolant flow PID regulation, and then controlling the reactor power according to the result of the three-impulse control.
2. The coordination control method of a nuclear power unit with an incremental state observer according to claim 1, wherein the specific process of obtaining the feedwater flow correction value for the feedwater flow PID adjustment is:
obtaining a water supply flow measurement value, calculating a water supply flow calculation value according to the unit load measurement value, and performing deviation calculation on the water supply flow calculation value and the water supply flow measurement value to obtain a water supply flow first deviation value; and adjusting the first deviation value of the water supply flow through an increment calculator and an inertia link, performing deviation calculation on the first deviation value of the water supply flow and a water supply flow set value obtained after fitting the water supply flow with a history operation database to obtain a second deviation value of the water supply flow, correcting the increment calculator by using the second deviation value of the water supply flow to obtain a first correction value, enabling the second deviation value of the water supply flow to be equal to zero, and finally taking the first correction value as a water supply flow correction value for PID adjustment of the water supply flow.
3. The nuclear power unit coordination control method with the incremental state observer according to claim 1, wherein the specific process of obtaining the unit load correction value for unit load PID adjustment is as follows:
obtaining a unit load measured value, performing deviation calculation on a unit load set value and the unit load measured value to obtain a unit load first deviation value, performing deviation calculation on the unit load calculated value and the unit load measured value to obtain a unit load second deviation value, performing weighted calculation on the unit load first deviation value and the unit load second deviation value, and obtaining a unit load corrected value for PID adjustment of the unit load.
4. The coordinated control method of a nuclear power unit with an incremental status observer according to claim 1, wherein the specific process of obtaining a loop coolant flow correction value for a loop coolant flow PID adjustment is:
obtaining a loop coolant flow measurement value, calculating a loop coolant flow calculation value according to the reactor power measurement value, and performing deviation calculation on the loop coolant flow calculation value and the loop coolant flow measurement value to obtain a loop coolant flow first deviation value; and regulating the first deviation value of the flow of the loop coolant through an incremental calculator and an inertia link, performing deviation calculation on the first deviation value and a loop coolant flow set value obtained after fitting the first deviation value and the history operation database to obtain a second deviation value of the flow of the loop coolant, correcting the incremental calculator by using the second deviation value of the flow of the loop coolant to obtain a second correction value, enabling the second deviation value of the flow of the loop coolant to be equal to zero, and finally using the second correction value as a loop coolant flow correction value for PID regulation of the flow of the loop coolant.
5. The nuclear power unit coordination control method with an incremental state observer according to claim 1, wherein the specific process of obtaining the power correction value for the reactor power PID adjustment is:
and obtaining a reactor power measurement value, performing deviation calculation on the reactor power set value and the reactor power measurement value to obtain a reactor power deviation value, and calculating a power correction value for PID (proportion integration differentiation) adjustment of the reactor power according to the reactor power deviation value.
6. The nuclear power unit coordination control system with the incremental state observer is characterized by comprising a first calculation module (37), a second calculation module (38), a third calculation module (39) and a fourth calculation module (40), wherein the first calculation module (37), the second calculation module (38), the third calculation module (39) and the fourth calculation module (40) are sequentially connected.
7. The nuclear power unit coordination control system with incremental status observer of claim 6, wherein the first computing module (37) comprises a feedwater flow historic operation database module (1), a feedwater flow measurement module (2), a feedwater flow setting module (3), a first deviation module (4), a second deviation module (5), a first function solver (11), a first PID module (15), a first incremental calculator (20), a second incremental calculator (21), a first inertial link module (24), and a second inertial link module (25);
the output end of the water supply flow history operation database module (1) is communicated with the input end of the water supply flow setting module (3); the water supply flow setting module (3) is connected with the first input end of the first deviation module (4), the output end of the first deviation module (4) is connected with the input end of the first increment calculator (20) and the input end of the second increment calculator (21), the output end of the water supply flow measuring module (2) is connected with the first input end of the second deviation module (5), the output end of the second deviation module (5) is connected with the input end of the first increment calculator (20), the output end of the first increment calculator (20) is connected with the input end of the first inertia link module (24), the output end of the first inertia link module (24) is connected with the input end of the second increment calculator (21), the output end of the second increment calculator (21) is connected with the input end of the second inertia link module (25), the output end of the second inertia link module (25) is connected with the second input end of the first deviation module (4) and the input end of the first PID module (15), the output end of the first inertia link module (15) is connected with the first PID module (11), and the load solving function solving module (11) is connected with the input end of the first PID module (11).
8. The nuclear power unit coordination control system with incremental status observer of claim 7, wherein the second calculation module (38) includes a third deviation module (6), a fourth deviation module (7), a second function solver (12), a summation calculator (14), a first T module (18), a unit load measurement module (28), a unit load setting module (29), and a unit load manual/automatic master module (35);
the second output end of the unit load measuring module (28) and the first output end of the unit load setting module (29) are communicated with the input end of the third deviation module (6), the second output end of the unit load setting module (29) is communicated with the first input end of the fourth deviation module (7), the output end of the third deviation module (6) and the output end of the fourth deviation module (7) are communicated with the input end of the summation calculator (14), the output end of the summation calculator (14) is communicated with the second input end of the first T module (18), the output end of the first T module (18) is communicated with the input end of the unit load manual/automatic master control module (35), the output end of the unit load manual/automatic master control module (35) is communicated with the first input end of the second T module (19), and the input end of the second function solver (12) is communicated with the first output end of the power setting module (30), and the output end of the second function solver (12) is communicated with the second input end of the fourth deviation module (7).
9. The nuclear power unit coordination control system with incremental status observer of claim 8, wherein the third computing module (39) includes a fifth deviation module (8), a second PID module (16), a second T module (19), a power setting module (30), a power measurement module (31), and a reactor power manual/automatic master module (36);
the second output end of the power setting module (30) and the first output end of the power measuring module (31) are communicated with the input end of the fifth deviation module (8), the output end of the fifth deviation module (8) is communicated with the input end of the second PID module (16), the output end of the second PID module (16) is communicated with the second input end of the second T module (19), the output end of the second T module (19) is communicated with the input end of the reactor power manual/automatic main control module (36), and the third input end of the second T module (19) is communicated with the output end of the third PID module (17).
10. The nuclear power unit coordination control system with incremental status observer of claim 9, wherein the fourth calculation module (40) includes a sixth deviation module (9), a seventh deviation module (10), a third function solver (13), a third PID module (17), a third incremental calculator (22), a fourth incremental calculator (23), a third inertia link module (26), a fourth inertia link module (27), a loop coolant flow measurement module (32), a loop coolant flow history database module (33), and a loop coolant flow setting module (34);
the input end of the third function solver (13) is communicated with the second output end of the power measuring module (31), the output end of the third function solver (13) is communicated with the first input end of the fourth deviation module (6), the output end of the first loop coolant flow measuring module (21) and the output end of the first loop coolant flow measuring module (32) are communicated with the input end of the sixth deviation module (9), the output end of the sixth deviation module (9) is communicated with the first input end of the third increment calculator (22), the output end of the third increment calculator (22) is communicated with the input end of the third inertia link module (26), the output end of the third inertia link module (26) is communicated with the input end of the fourth increment calculator (23), the output end of the fourth increment calculator (23) is communicated with the input end of the fourth inertia link module (27), the first output end of the fourth inertia link module (27) is communicated with the input end of the third PID module (17), the output end of the fourth inertia link (27) is communicated with the output end of the seventh inertia link (10) and the seventh inertia link (10) is calculated, an output of a loop coolant flow history operating database module (33) communicates with an input of a loop coolant flow setting module (34), and an output of the loop coolant flow setting module (34) communicates with a second input of the seventh deviation module (10).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310557355.XA CN116610031A (en) | 2023-05-17 | 2023-05-17 | Nuclear power unit coordination control system and method with incremental state observer |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310557355.XA CN116610031A (en) | 2023-05-17 | 2023-05-17 | Nuclear power unit coordination control system and method with incremental state observer |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN116610031A true CN116610031A (en) | 2023-08-18 |
Family
ID=87682923
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310557355.XA Pending CN116610031A (en) | 2023-05-17 | 2023-05-17 | Nuclear power unit coordination control system and method with incremental state observer |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN116610031A (en) |
-
2023
- 2023-05-17 CN CN202310557355.XA patent/CN116610031A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Sun et al. | Direct energy balance based active disturbance rejection control for coal-fired power plant | |
| CN101709869B (en) | Hybrid control method for superheat steam temperature system of coal-fired boiler | |
| CN109212974A (en) | The robust fuzzy of Interval time-varying delay system predicts fault tolerant control method | |
| WO2022105356A1 (en) | Method and system, having incremental adjustment function, for adjusting control rod of nuclear power unit | |
| CN112382418B (en) | High-temperature gas cooled reactor helium flow control system and method with incremental adjustment function | |
| CN100545772C (en) | A kind of coal-burning boiler system mixing control method | |
| CN108227500A (en) | A kind of control method for coordinating and system of the quick peak regulation of fired power generating unit | |
| Wei et al. | ${H} _ {\infty} $-LQR-Based Coordinated Control for Large Coal-Fired Boiler–Turbine Generation Units | |
| CN101709867B (en) | Hybrid control method for drum water level system of coal-fired boiler | |
| CN101738936A (en) | Control strategy of self-adaption digital closed loop applied in UPS | |
| CN101709863B (en) | Hybrid control method for furnace pressure system of coal-fired boiler | |
| CN111654047A (en) | Pumped storage and electrochemical storage combined participation power grid load frequency control method based on active disturbance rejection | |
| Du et al. | Design of PI controller for a class of discrete cascade control systems | |
| CN110579968A (en) | Prediction control strategy for ultra-supercritical unit depth peak regulation coordination system | |
| CN116610031A (en) | Nuclear power unit coordination control system and method with incremental state observer | |
| CN113448248A (en) | Intelligent control method for flexibility and deep peak regulation of thermal power generating unit | |
| CN105207220B (en) | A kind of tapping voltage regulation and control method based on progressive learning | |
| Zadeh et al. | Load frequency control in interconnected power system by nonlinear term and uncertainty considerations by using of harmony search optimization algorithm and fuzzy-neural network | |
| CN114513017B (en) | Distributed tracking method and system for power distribution network instructions of alternating current-direct current micro-grid | |
| CN106647247B (en) | A kind of control algolithm suitable for servo controller | |
| CN112435768B (en) | Method and system for controlling water supply flow of nuclear power generating unit with incremental adjusting function | |
| Li et al. | AGC fuzzy PID control strategy based on Parameter Optimization | |
| Tan et al. | Sliding mode control of steam generator water level based on particle swarm optimization | |
| Peng et al. | Multi-channel Flow Ratio Control Method of Water and Fertilizer Integrated Machine Based on Active Disturbance Rejection Control | |
| Xu et al. | Process control optimization for hydroelectric power based on neural network algorithm |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |