CN111262280A - Modeling and analyzing method for primary frequency modulation of pressurized water reactor nuclear power unit - Google Patents
Modeling and analyzing method for primary frequency modulation of pressurized water reactor nuclear power unit Download PDFInfo
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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
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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: analyzing the mutual influence factors among parameters in the primary frequency modulation action process according to the primary frequency modulation action principle of the nuclear power unit, and giving out a model structure among the parameters by combining an operation mechanism; and meanwhile, selecting a typical working point according to the primary frequency modulation application range, carrying out a characteristic test, carrying out parameter identification on the model by using test data, establishing a primary frequency modulation dynamic model near the typical working point, carrying out simulation analysis through the established primary frequency modulation dynamic model, and evaluating the primary frequency modulation performance and the influence on the safety performance of the unit. Compared with the prior art, the modeling method provided by the invention has the advantages of simple and convenient modeling, capability of more accurately reproducing actual operating 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 analyzing method for primary frequency modulation of a pressurized water reactor nuclear power unit.
Background
In recent years, the scale of a power grid is continuously enlarged, and in addition, new energy power such as wind power, solar energy and the like is continuously incorporated, so that the structure of the power grid is greatly changed. The load peak-valley difference of the power grid is gradually increased, the frequency fluctuation is more and 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 a power grid, a plurality of thermal power generating units are optimized aiming at the primary frequency modulation performance, particularly the large frequency difference performance. Although the nuclear power generating unit in China is designed with a primary frequency modulation function, the nuclear power generating unit always runs at a basic load in consideration of the safety of a primary loop system (a nuclear island part). With the increasing installed capacity of nuclear power generating units in China, the requirement of a power grid on the participation of the nuclear power generating units in primary frequency modulation is 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 mechanism models 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, is complex in modeling and difficult in model solving, and particularly needs a large amount of formula derivation and theoretical calculation for a nuclear reactor mechanism model, so that the method is inconvenient for engineering practical analysis and application; in addition, a mechanism model of design parameters is completely adopted for simulation, although the trend is consistent with the reality, the trend is separated from the actual operation data, the inherent characteristics of the system cannot be completely obtained, and a 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 power unit.
The purpose of the invention can be realized by the following technical scheme:
a modeling and analyzing method for primary frequency modulation of a pressurized water reactor nuclear power unit comprises the following steps: analyzing the mutual influence factors among parameters in the primary frequency modulation action process according to the primary frequency modulation action principle of the nuclear power unit, and giving out a model structure among the parameters by combining an operation mechanism;
and simultaneously, selecting a typical working point according to the primary frequency modulation application range, carrying out a characteristic test, carrying out parameter identification on the model by using test data, establishing a primary frequency modulation dynamic model near the typical working point, and carrying out 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 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 within the primary frequency modulation application range, performing a characteristic test, and acquiring a characteristic curve;
step 4, identifying parameters of each sub-model by using a particle swarm identification algorithm to finally obtain a primary frequency modulation dynamic model;
and 5, simulating according to the obtained primary frequency modulation dynamic model, and evaluating the primary frequency modulation performance and the influence on the safety performance of the nuclear power unit by combining the primary frequency modulation examination requirement. .
Preferably, the two inputs are a steam turbine flow instruction and a power rod position instruction, and the six outputs are a unit load, a main steam pressure, a pressurizer 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 steam turbine flow instruction characteristic and a rod position instruction characteristic, and the model structure of the step 2 is described by using a transfer function of multi-order inertia plus pure delay, as shown in formula (1):
wherein K is a gain factor; t is1、T2Is the inertia time; n is1、n2Is the system order; τ is pure delayAnd (5) delaying time.
Preferably, the step 3 specifically comprises:
and selecting a typical working condition point to perform steam turbine flow characteristic and power rod position characteristic tests by combining the primary frequency modulation application range, and respectively obtaining change curves of group load, main steam pressure, pressure of a pressure stabilizer, liquid level of the pressure stabilizer, rod position of the power rod, axial power deviation and average temperature of a coolant when the steam turbine flow and the rod position change.
Preferably, the typical operating point is a plurality of operating conditions within the primary frequency modulation application range.
Preferably, the step 4 specifically includes:
and (3) carrying out model parameter identification on the model structure of the steam turbine flow and rod position change time group load, main steam pressure, pressure of a voltage stabilizer, liquid level of the voltage stabilizer, rod position of a power rod, axial power deviation and average temperature of a coolant described by the formula (1) by applying a particle swarm identification algorithm, and further obtaining a primary frequency modulation dynamic response model of the steam turbine.
Compared with the prior art, the invention has the following advantages:
the invention determines action variables and influencing factors on the basis of analyzing a primary frequency modulation action mechanism, and gives a model structure by combining the characteristics of a thermodynamic system. And meanwhile, performing characteristic tests at typical working points, and identifying the structural parameters of the model by adopting a particle swarm identification algorithm to finally obtain a primary frequency modulation dynamic model. Compared with a mechanism analysis method, the method adopts a mechanism and identification combined modeling method, avoids a large amount of theoretical derivation calculation, reduces modeling complexity, and simultaneously identifies model parameters by using an identification algorithm, ensures model precision and can more accurately reproduce actual operating 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 generating unit.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, not all, embodiments of the present invention. All other embodiments, which can be obtained by a person skilled in the art without any inventive step based on the embodiments of the present invention, shall fall within the scope of protection of the present invention.
The invention provides a simple modeling analysis method suitable for primary frequency modulation of a pressurized water reactor nuclear power unit. Analyzing the mutual influence factors among parameters in the primary frequency modulation action process according to the primary frequency modulation action principle of the nuclear power unit, and giving out a model structure among the parameters by combining an operation mechanism; and meanwhile, selecting a typical working point according to the primary frequency modulation application range, carrying out a characteristic test, and carrying out parameter identification on the model by using test data to establish a primary frequency modulation dynamic model near the typical working point. The method is simple and convenient in structure and easy for engineering analysis, and can more accurately reflect the actual action condition by identifying the parameters according to the characteristic test data. The specific modeling scheme is as follows:
1. and determining the influencing factors by combining a primary frequency modulation mechanism.
FIG. 1 is a schematic diagram of a primary frequency modulation action of a nuclear power unit, wherein when a frequency deviation occurs in a power grid, a primary frequency modulation load instruction is acted on a steam turbine flow instruction through a PID power controller to rapidly adjust a unit load, a coolant average temperature set value of a nuclear island (a loop) is a function of the unit load, after 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 increases or decreases at a certain rate to adjust reactor power, so that tracking of the reactor power on the steam turbine load is realized. In this process, the unit load, the main steam pressure, the coolant mean temperature and the axial power deviation fluctuate. Meanwhile, the fluctuation of the average temperature of the coolant can affect 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 basically not changed. In combination with actual operation conditions, main steam pressure, pressure of the pressure stabilizer, liquid level of the pressure stabilizer, rod position of the power rod, axial power deviation and average temperature of the coolant are main parameters for monitoring unit safety. 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, pressure of a voltage stabilizer, liquid level of the voltage stabilizer, axial power deviation and average temperature of a coolant) system model.
2. And determining a model structure.
Lumped parameter descriptions in integral order transfer function models are commonly employed for thermodynamic systems. The primary frequency modulation model is divided into two typical thermodynamic processes of steam turbine flow instruction characteristic and rod position instruction characteristic, and the model structure can be described by adopting a transfer function of multi-order inertia and pure delay, as shown in formula 1:
it should be noted that the steam turbine flow command to the unit load model is modeled according to the distribution of the high and low pressure cylinders and the flow distribution.
3. And (5) carrying out a characteristic test to obtain a characteristic curve.
And selecting typical working condition points (a plurality of working condition points) to perform steam turbine flow characteristic and power rod position characteristic tests in combination with the primary frequency modulation application range, and respectively obtaining change curves of group loads, main steam pressure, pressure of a pressure stabilizer, liquid level of the pressure stabilizer, rod position of a power rod, axial power deviation and average temperature of a coolant when the steam turbine flow and the rod position change.
4. Identifying each sub-model parameter.
Model parameters are identified by using identification methods such as particle swarm and ant colony for model structures of the steam turbine load, main steam pressure, pressure stabilizer pressure, liquid level of the pressure stabilizer, rod position of the power rod, axial power deviation and average temperature of the coolant when the steam turbine flow and the rod position change are described by the formula 1, and then a primary frequency modulation dynamic response model of the unit is obtained.
DETAILED DESCRIPTION OF EMBODIMENT (S) OF INVENTION
Taking a domestic pressurized water reactor nuclear power unit with a certain rated load (electric power) Pe being 650MW as an example, the steam turbine of the unit is provided with 1 high pressure cylinder and 3 low pressure cylinders, and the flow rate ratio of the high pressure cylinder to the low pressure cylinder is 0.3148/0.2284. According to the power grid assessment requirement, the unit primary frequency modulation application range 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-19.8 MW.
In this example, 80% P0, 90% P0 and 97% P0 were selected as typical operating points for characteristic tests, and only 90% P0 operating point was selected for illustration. Under the working condition, disturbance tests of +/-1% of steam turbine flow instructions and +/-3 steps of rod positions 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.
Combining formula (1), adopting the particle swarm identification algorithm to respectively identify the unit load, main steam pressure, pressurizer liquid level, axial power deviation and coolant average temperature response curve under the steam turbine flow instruction disturbance and the rod position disturbance, wherein the identification result is shown in table 1, wherein table 1 is the unit primary frequency modulation model parameter under 90% P0 load:
TABLE 1
The overall model structure is shown in fig. 2:
while the invention has been described with reference to specific embodiments, the invention is not limited thereto, and various equivalent modifications and substitutions can be easily made by those skilled in the art within the technical scope of the invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (7)
1. A modeling and analyzing method for primary frequency modulation of a pressurized water reactor nuclear power unit is characterized by comprising the following steps: analyzing the mutual influence factors among main parameters in the primary frequency modulation action process according to the primary frequency modulation action principle of the nuclear power unit, and giving out a model structure among the parameters by combining an operation mechanism;
and simultaneously, selecting a typical working point according to the primary frequency modulation application range, carrying out a characteristic test, carrying out parameter identification on the model by using test data, establishing a primary frequency modulation dynamic model near the typical working point, and carrying out simulation analysis through the established primary frequency modulation dynamic model.
2. The modeling and analyzing method for the primary frequency modulation of the pressurized water reactor nuclear power generating set according to claim 1, wherein 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 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 within a primary frequency modulation application range, and acquiring a characteristic curve;
step 4, identifying parameters of each sub-model by using a particle swarm identification algorithm to finally obtain a primary frequency modulation dynamic model;
and 5, simulating according to the obtained primary frequency modulation dynamic model, and evaluating the primary frequency modulation performance and the influence on the safety performance of the nuclear power unit by combining the primary frequency modulation examination requirement.
3. The modeling and analysis method for the primary frequency modulation of a pressurized water reactor nuclear power plant as claimed in claim 2, wherein the two inputs are a steam turbine flow command and a power rod position command, and the six outputs are a plant load, a main steam pressure, a pressurizer liquid level, an axial power deviation and a coolant average temperature.
4. The modeling and analyzing method for the primary frequency modulation of the pressurized water reactor nuclear power generating set according to claim 2, wherein the primary frequency modulation model is divided into two typical thermodynamic processes of steam turbine flow instruction characteristic and rod position instruction characteristic, and the model structure of the step 2 is described by using a transfer function of multi-order inertia plus pure delay, as shown in formula (1):
wherein K is a gain factor; t is1、T2Is the inertia time; n is1、n2Is the system order; τ is the pure delay time.
5. The modeling and analyzing method for the primary frequency modulation of the pressurized water reactor nuclear power generating set according to claim 2, wherein the step 3 specifically comprises:
and selecting a typical working condition point to perform steam turbine flow characteristic and power rod position characteristic tests by combining the primary frequency modulation application range, and respectively obtaining change curves of group load, main steam pressure, pressure of a pressure stabilizer, liquid level of the pressure stabilizer, rod position of the power rod, axial power deviation and average temperature of a coolant when the steam turbine flow and the rod position change.
6. The modeling and analysis method for the primary frequency modulation of the pressurized water reactor nuclear power generating unit according to claim 5, wherein the typical operating point is a plurality of operating conditions within the primary frequency modulation application range.
7. The modeling and analyzing method for the primary frequency modulation of the pressurized water reactor nuclear power generating set according to claim 4, wherein the step 4 specifically comprises:
and (3) carrying out model parameter identification on the model structure of the steam turbine flow and rod position change time group load, main steam pressure, pressure of a voltage stabilizer, liquid level of the voltage stabilizer, rod position of a power rod, axial power deviation and average temperature of a coolant described by the formula (1) by applying a particle swarm identification algorithm, and further obtaining a primary frequency modulation dynamic response model of the steam turbine.
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113675896A (en) * | 2021-08-17 | 2021-11-19 | 华能山东石岛湾核电有限公司 | Method and device for adjusting power transmission power of 'machine-following-pile' mode power grid |
| WO2022105356A1 (en) * | 2020-11-20 | 2022-05-27 | 西安热工研究院有限公司 | Method and system, having incremental adjustment function, for adjusting control rod of nuclear power unit |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| WO2013163840A1 (en) * | 2012-05-04 | 2013-11-07 | 浙江大学 | Nonlinear parameter varying (npv) model identification method |
| CN106773666A (en) * | 2016-11-11 | 2017-05-31 | 中国电力科学研究院 | A kind of model parameter acquisition methods for presurized water reactor primary Ioops system |
-
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Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| WO2013163840A1 (en) * | 2012-05-04 | 2013-11-07 | 浙江大学 | Nonlinear parameter varying (npv) model identification method |
| CN106773666A (en) * | 2016-11-11 | 2017-05-31 | 中国电力科学研究院 | A kind of model parameter acquisition methods for presurized water reactor primary Ioops system |
Non-Patent Citations (1)
| Title |
|---|
| 侯晓宁: "1000MW 超超临界机组主汽温建模及其精度研究" * |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2022105356A1 (en) * | 2020-11-20 | 2022-05-27 | 西安热工研究院有限公司 | Method and system, having incremental adjustment function, for adjusting control rod of nuclear power unit |
| CN113675896A (en) * | 2021-08-17 | 2021-11-19 | 华能山东石岛湾核电有限公司 | Method and device for adjusting power transmission power of 'machine-following-pile' mode power grid |
| CN113675896B (en) * | 2021-08-17 | 2022-05-27 | 华能山东石岛湾核电有限公司 | Method and device for adjusting power transmission power of 'machine-following-pile' mode power grid |
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