CN111262280B - Modeling and analysis method for primary frequency modulation of pressurized water reactor nuclear motor unit - Google Patents
Modeling and analysis method for primary frequency modulation of pressurized water reactor nuclear motor unit Download PDFInfo
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- CN111262280B CN111262280B CN201811453436.0A CN201811453436A CN111262280B CN 111262280 B CN111262280 B CN 111262280B CN 201811453436 A CN201811453436 A CN 201811453436A CN 111262280 B CN111262280 B CN 111262280B
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- H—ELECTRICITY
- H02—GENERATION; CONVERSION OR DISTRIBUTION OF ELECTRIC POWER
- H02J—CIRCUIT ARRANGEMENTS OR SYSTEMS FOR SUPPLYING OR DISTRIBUTING ELECTRIC POWER; SYSTEMS FOR STORING ELECTRIC ENERGY
- H02J3/00—Circuit arrangements for ac mains or ac distribution networks
- H02J3/38—Arrangements for parallely feeding a single network by two or more generators, converters or transformers
- H02J3/46—Controlling of the sharing of output between the generators, converters, or transformers
- H02J3/48—Controlling the sharing of the in-phase component
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- H—ELECTRICITY
- H02—GENERATION; CONVERSION OR DISTRIBUTION OF ELECTRIC POWER
- H02J—CIRCUIT ARRANGEMENTS OR SYSTEMS FOR SUPPLYING OR DISTRIBUTING ELECTRIC POWER; SYSTEMS FOR STORING ELECTRIC ENERGY
- H02J3/00—Circuit arrangements for ac mains or ac distribution networks
- H02J3/24—Arrangements for preventing or reducing oscillations of power in networks
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Abstract
The invention relates to a modeling and analyzing method for primary frequency modulation of a pressurized water reactor nuclear power unit, which comprises the following steps: according to the primary frequency modulation action principle of the nuclear power unit, analyzing the mutual influence factors among parameters in the primary frequency modulation action process, and giving out a model structure among the parameters by combining an operation mechanism; and meanwhile, according to the primary frequency modulation application range, selecting a typical working point, performing a characteristic test, performing parameter identification on the model by using test data, establishing a primary frequency modulation dynamic model near the typical working point, and performing simulation analysis through the established primary frequency modulation dynamic model to evaluate primary frequency modulation performance and influence on unit safety performance. Compared with the prior art, the modeling method provided by the invention has the advantages of simplicity and convenience in modeling, capability of more accurately reproducing the actual operation characteristics and the like.
Description
Technical Field
The invention relates to a pressurized water reactor nuclear power unit simulation technology, in particular to a modeling and analysis method for primary frequency modulation of a pressurized water reactor nuclear power unit.
Background
In recent years, the power grid scale is continuously enlarged, new energy sources such as wind power, solar energy and the like are continuously combined, and the power grid structure is greatly changed. The peak-valley difference of the power grid load is gradually increased, the frequency fluctuation is more frequent, and higher requirements are provided for the primary frequency modulation function of the grid-connected unit. In order to ensure the safety and stability of the power grid, many thermal power generating units optimize primary frequency modulation performance, particularly large frequency difference performance. Although the nuclear power unit in China is designed with a primary frequency modulation function, the unit always operates with a basic load due to the consideration of the safety of a primary loop system (a nuclear island part). With the continuous increase of the capacity of the nuclear power unit in China, the requirements of the power grid on the participation of the nuclear power unit in primary frequency modulation are more and more urgent.
In order to evaluate the safety of the nuclear power unit during primary frequency modulation action, a mechanism analysis method is mainly applied at present to establish a mechanism model of a nuclear island and a conventional island according to design parameters, and primary frequency modulation performance evaluation is carried out on the basis. On one hand, the mechanism modeling method needs to deeply understand the operation mechanism of a modeling object, modeling is complex, model solving is difficult, particularly a nuclear reactor mechanism model needs a large amount of formula deduction and theoretical calculation, and engineering practical analysis and application are inconvenient; in addition, the simulation is carried out by completely adopting a mechanism model of design parameters, and although the trend is consistent with the actual trend, the intrinsic characteristics of the system can not be completely obtained without the actual operation data, and certain deviation still exists between the simulation result and the actual operation result.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provide a modeling and analyzing method for primary frequency modulation of a pressurized water reactor nuclear motor unit.
The aim of the invention can be achieved by the following technical scheme:
a modeling and analyzing method for primary frequency modulation of a pressurized water reactor nuclear motor unit comprises the following steps: according to the primary frequency modulation action principle of the nuclear power unit, analyzing the mutual influence factors among parameters in the primary frequency modulation action process, and giving out a model structure among the parameters by combining an operation mechanism;
and meanwhile, according to the primary frequency modulation application range, selecting a typical working point, performing a characteristic test, performing parameter identification on the model by using test data, establishing a primary frequency modulation dynamic model near the typical working point, and performing simulation analysis through the established primary frequency modulation dynamic model.
Preferably, the method specifically comprises the following steps:
step 1, determining influence factors by combining a primary frequency modulation mechanism, and simplifying a primary frequency modulation model of a given nuclear power unit into a two-input and six-output system model;
step 2, determining a model structure;
step 3, selecting typical working condition points in the primary frequency modulation application range, and performing a characteristic test to obtain a characteristic curve;
step 4, identifying parameters of each sub-model by using a particle swarm identification algorithm, and finally obtaining a primary frequency modulation dynamic model;
and 5, simulating according to the obtained primary frequency modulation dynamic model, and evaluating primary frequency modulation performance and influence on the safety performance of the nuclear power unit by combining with the primary frequency modulation checking requirement. .
Preferably, the two inputs are a turbine flow command and a power rod position command, and the six outputs are a unit load, a main steam pressure, a stabilizer liquid level, an axial power deviation and a coolant average temperature.
Preferably, the primary frequency modulation model is divided into two typical thermodynamic processes of a turbine flow instruction characteristic and a rod position instruction characteristic, and the model structure of the step 2 is described by adopting a transfer function of multi-order inertia plus pure delay, as shown in a formula (1):
wherein K is a gain factor; t (T) 1 、T 2 Is the inertia time; n is n 1 、n 2 Is the system order; τ is the pure delay time.
Preferably, the step 3 specifically includes:
and selecting typical working points to perform steam turbine flow characteristics and power rod position characteristics by combining a primary frequency modulation application range, and respectively obtaining change curves of unit load, main steam pressure, voltage stabilizer liquid level, power rod position, axial power deviation and average coolant temperature when the steam turbine flow and the rod position are changed.
Preferably, the typical operating point is a plurality of operating conditions within a primary frequency modulation application range.
Preferably, the step 4 specifically includes:
and (3) performing model parameter identification on a model structure of the unit load, the main steam pressure, the voltage stabilizer liquid level, the power rod position, the axial power deviation and the average coolant temperature when the steam turbine flow and the rod position are changed, which are described by an application formula (1), by using a particle swarm identification algorithm, so as to obtain a unit primary frequency modulation dynamic response model.
Compared with the prior art, the invention has the following advantages:
on the basis of analyzing the primary frequency modulation action mechanism, the invention determines action variables and influencing factors and combines the thermodynamic system characteristics to give a model structure. And simultaneously, carrying out characteristic test at a typical working point, and identifying the model structural parameters by adopting a particle swarm identification algorithm to finally obtain the primary frequency modulation dynamic model. Compared with a mechanism analysis method, the method adopts a mechanism-identification composite modeling method, avoids a large amount of theoretical deduction calculation, reduces modeling complexity, simultaneously utilizes an identification algorithm to identify model parameters, ensures model precision, and can more accurately reproduce actual operation characteristics.
Drawings
FIG. 1 is a primary frequency modulation schematic diagram of a nuclear power unit;
fig. 2 is a schematic diagram of a primary frequency modulation model structure of a nuclear power unit.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and fully with reference to the accompanying drawings, in which it is evident that the embodiments described are some, but not all embodiments of the invention. 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.
The invention provides a simple modeling analysis method suitable for primary frequency modulation of a pressurized water reactor nuclear motor unit. According to the primary frequency modulation action principle of the nuclear power unit, analyzing the mutual influence factors among parameters in the primary frequency modulation action process, and giving out a model structure among the parameters by combining an operation mechanism; and meanwhile, according to the primary frequency modulation application range, selecting a typical working point, performing a characteristic test, and performing parameter identification on the model by using test data to establish a primary frequency modulation dynamic model near the typical working point. The method has simple structure, is easy for engineering analysis, and can accurately reflect the actual action condition by carrying out parameter identification according to the characteristic test data. The specific modeling scheme is as follows:
1. and determining influencing factors by combining a primary frequency modulation mechanism.
FIG. 1 is a schematic diagram of primary frequency modulation operation of a nuclear power unit, wherein when a power grid is subjected to frequency deviation, a primary frequency modulation load command acts on a turbine flow command through a PID power controller to quickly adjust the unit load, a nuclear island (primary loop) coolant average temperature set value is a function of the unit load, when the unit load changes, the coolant average temperature set value changes, and when the deviation from an actual value exceeds a dead zone, a power adjusting rod rises or falls at a certain rate to adjust the reactor power, so that the reactor power can track the turbine load. During this process, the unit load, main steam pressure, coolant average temperature and axial power deviations all fluctuate. And the fluctuation of the average temperature of the coolant can influence the pressure and liquid level change of the pressure stabilizer. In addition, the rapid duration of the primary frequency modulation action process is short, so that parameters such as boric acid concentration, coolant flow and the like related to nuclear reaction are not changed basically. The main steam pressure, the pressure of the pressure stabilizer, the liquid level of the pressure stabilizer, the position of the power rod, the axial power deviation and the average temperature of the coolant are main parameters for monitoring the safety of the unit. Therefore, the primary frequency modulation model of the nuclear power unit provided by the invention can be simplified into a two-input (steam turbine flow instruction and power rod position instruction) and six-output (unit load, main steam pressure, voltage stabilizer liquid level, axial power deviation and coolant average temperature) system model.
2. A model structure is determined.
Concentrated parametric descriptions in integer order transfer function models are commonly employed for thermodynamic systems. The primary frequency modulation model is divided into two typical thermodynamic processes of a turbine flow instruction characteristic and a rod position instruction characteristic, and the model structure can be described by adopting a transfer function of multi-order inertia plus pure delay, as shown in formula 1:
in addition, the turbine flow command to the unit load model is modeled according to the distribution of the high-pressure cylinder and the low-pressure cylinder and the flow distribution.
3. And performing a characteristic test to obtain a characteristic curve.
And selecting a typical working point(s) to perform a turbine flow characteristic and a power rod position characteristic test by combining the primary frequency modulation application range, and respectively obtaining a unit load, a main steam pressure, a voltage stabilizer liquid level, a power rod position, an axial power deviation and a change curve of the average temperature of the coolant when the turbine flow and the rod position are changed.
4. Identifying each sub-model parameter.
And (3) performing model parameter identification on model structures of the turbine load, the main steam pressure, the voltage stabilizer liquid level, the power rod position, the axial power deviation and the average coolant temperature when the turbine flow and the rod position are changed, which are described by an application formula 1, by using identification methods of particle swarm, ant colony and the like, so as to obtain a primary frequency modulation dynamic response model of the turbine.
DETAILED DESCRIPTION OF EMBODIMENT (S) OF INVENTION
Taking a domestic rated load (electric power) pe=650 MW pressurized water reactor nuclear generator unit as an example, the turbine of the unit is provided with 1 high-pressure cylinder and 3 low-pressure cylinders, and the flux ratio of the high-pressure cylinder to the low-pressure cylinder is 0.3148/0.2284. According to the power grid assessment requirements, the primary frequency modulation application range of the unit is required to be 80% -100% P. In the load (P0 is rated nuclear power) range, the frequency modulation dead zone is +/-0.067 Hz, and the maximum primary frequency modulation action amount is required to be 3%Pe=19.8MW.
In this example, 80% p0, 90% p0, 97% p0 are chosen as typical operating points for the performance test, limited to the spread, and only 90% p0 is chosen for illustration. Under the working condition, disturbance tests of +/-1% of a turbine flow command and +/-3 steps of a rod position are respectively carried out, and six groups of variable characteristic curves of unit load, main steam pressure, pressure of a pressure stabilizer, liquid level of the pressure stabilizer, axial power deviation and average temperature of a coolant are obtained.
And (3) respectively identifying a unit load, a main steam pressure, a voltage stabilizer liquid level, an axial power deviation and a coolant average temperature response curve under the condition of turbine flow instruction disturbance and rod position disturbance by adopting a particle swarm identification algorithm according to a formula (1), wherein the identification result is shown in a table 1, and the table 1 is a unit primary frequency modulation model parameter under the load of 90%P0:
TABLE 1
The overall model structure is shown in fig. 2:
while the invention has been described with reference to certain preferred embodiments, it will be understood by those skilled in the art that various changes and substitutions of equivalents may be made and equivalents will be apparent to those skilled in the art without departing from the scope of the invention. Therefore, the protection scope of the invention is subject to the protection scope of the claims.
Claims (4)
1. A modeling and analysis method for primary frequency modulation of a pressurized water reactor nuclear motor unit, comprising: according to the primary frequency modulation action principle of the nuclear power unit, analyzing the interaction factors among main parameters in the primary frequency modulation action process, and giving out a model structure among the parameters by combining an operation mechanism;
according to the primary frequency modulation application range, selecting a typical working point, performing a characteristic test, performing parameter identification on a model by using test data, establishing a primary frequency modulation dynamic model near the typical working point, and performing simulation analysis through the established primary frequency modulation dynamic model;
the method specifically comprises the following steps:
step 1, determining influence factors by combining a primary frequency modulation mechanism, and simplifying a primary frequency modulation model of a given nuclear power unit into a two-input and six-output system model;
step 2, determining a model structure;
step 3, selecting typical working condition points to perform a characteristic test in a primary frequency modulation application range, and obtaining a characteristic curve;
step 4, identifying parameters of each sub-model by using a particle swarm identification algorithm, and finally obtaining a primary frequency modulation dynamic model;
step 5, simulating according to the obtained primary frequency modulation dynamic model, and evaluating primary frequency modulation performance and influence on the safety performance of the nuclear power unit by combining primary frequency modulation checking requirements;
the six outputs are unit load, main steam pressure, voltage stabilizer liquid level, axial power deviation and average coolant temperature;
the primary frequency modulation model is divided into two typical thermodynamic processes of a turbine flow instruction characteristic and a rod position instruction characteristic, the model structure of the step 2 is described by adopting a transfer function of multi-order inertia plus pure delay, and the transfer function is shown as a formula (1):
wherein K is a gain factor; t (T) 1 、T 2 Is the inertia time; n is n 1 、n 2 Is the system order; τ is the pure delay time.
2. The modeling and analysis method for primary frequency modulation of a pressurized water reactor nuclear motor unit according to claim 1, wherein the step 3 is specifically:
and selecting typical working points to perform steam turbine flow characteristics and power rod position characteristics by combining a primary frequency modulation application range, and respectively obtaining change curves of unit load, main steam pressure, voltage stabilizer liquid level, power rod position, axial power deviation and average coolant temperature when the steam turbine flow and the rod position are changed.
3. The modeling and analysis method for primary frequency modulation of a pressurized water reactor nuclear motor unit according to claim 2, wherein the typical operating point is a plurality of operating conditions within a primary frequency modulation application range.
4. The modeling and analysis method for primary frequency modulation of a pressurized water reactor nuclear motor unit according to claim 1, wherein the step 4 is specifically:
and (3) performing model parameter identification on a model structure of the unit load, the main steam pressure, the voltage stabilizer liquid level, the power rod position, the axial power deviation and the average coolant temperature when the steam turbine flow and the rod position are changed, which are described by an application formula (1), by using a particle swarm identification algorithm, so as to obtain a unit primary frequency modulation dynamic response model.
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| CN102146812A (en) * | 2010-02-09 | 2011-08-10 | 浙江省电力公司 | Actual-measurement modeling method for prime mover and speed governor thereof of electric power system |
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