CN117763979A - Nuclear power two-loop fluid system and electric power system joint simulation method and system - Google Patents
Nuclear power two-loop fluid system and electric power system joint simulation method and system Download PDFInfo
- Publication number
- CN117763979A CN117763979A CN202311412587.2A CN202311412587A CN117763979A CN 117763979 A CN117763979 A CN 117763979A CN 202311412587 A CN202311412587 A CN 202311412587A CN 117763979 A CN117763979 A CN 117763979A
- Authority
- CN
- China
- Prior art keywords
- electric power
- nuclear power
- loop fluid
- fluid system
- simulation
- 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
- 239000012530 fluid Substances 0.000 title claims abstract description 109
- 238000004088 simulation Methods 0.000 title claims abstract description 69
- 238000000034 method Methods 0.000 title claims abstract description 34
- 238000004891 communication Methods 0.000 claims abstract description 26
- 230000003993 interaction Effects 0.000 claims abstract description 19
- 238000004134 energy conservation Methods 0.000 claims abstract description 9
- 230000001105 regulatory effect Effects 0.000 claims description 8
- 230000008569 process Effects 0.000 description 12
- 238000010586 diagram Methods 0.000 description 5
- 239000003758 nuclear fuel Substances 0.000 description 5
- 239000002826 coolant Substances 0.000 description 4
- 238000011160 research Methods 0.000 description 4
- 230000005540 biological transmission Effects 0.000 description 3
- 230000008859 change Effects 0.000 description 3
- 230000008878 coupling Effects 0.000 description 3
- 238000010168 coupling process Methods 0.000 description 3
- 238000005859 coupling reaction Methods 0.000 description 3
- 239000011159 matrix material Substances 0.000 description 3
- 238000012545 processing Methods 0.000 description 3
- 238000004364 calculation method Methods 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 230000006870 function Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 239000012636 effector Substances 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 238000010295 mobile communication Methods 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 230000000704 physical effect Effects 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
Landscapes
- Management, Administration, Business Operations System, And Electronic Commerce (AREA)
Abstract
The invention discloses a combined simulation method and a system for a nuclear power two-loop fluid system and an electric power system, wherein the method comprises the following steps: modeling a nuclear power two-loop fluid system according to a mass conservation equation, a momentum conservation equation and an energy conservation equation, and modeling a steam turbine generator in the nuclear power two-loop fluid system through an isentropic enthalpy drop model; modeling the electric power system, defining an interaction interface and a communication mode of the nuclear power two-loop fluid system and the electric power system, and respectively performing single-step simulation on the modeled nuclear power two-loop fluid system and the electric power system and interacting through the interaction interface and the communication mode.
Description
Technical Field
The invention belongs to the technical field of power system simulation, and particularly relates to a combined simulation method and system of a nuclear power two-loop fluid system and a power system.
Background
The fluid network theory was first developed and in 1957, lu Erman and Grosvenor's research into fluid network systems was conducted by analogy with fluid network systems and power grid systems. Foreign research on fluid networks began earlier by the eighties of the twentieth century, relatively mature fluid network theory had been developed, simulation of fluid networks was achieved, and fluid network simulation software was developed based on the fluid network theory. The foreign simulation software mainly comprises: APROS simulation platform, JTopmeret software of GSE company, flowmaster software of Siemens company, simulink module of Matlab, and relay 5 calculation program. The development of the fluid network in China is relatively late compared with the development of the fluid network in China, but through continuous efforts of scientific researchers, the research and development of decades are carried out, and the research on the fluid network in China is also carried out in China. The domestic simulation software mainly comprises: ADMIRE-F software of Guangdong imitation science and technology Co., ltd, cyberSim software of tetragonal Co., ltd, STAR-90 software of Hua imitation science and technology Co., ltd and RinSim simulation platform of nuclear power operation research institute.
The two-loop fluid network simulation of the nuclear power device mainly adopts a node pressure method, a continuous area with basically the same thermodynamic and hydraulic parameters in a pipe network is divided into nodes, flow transmission among the nodes is realized through flow lines, and finally the pipe network is divided into a fluid network consisting of basic elements such as internal nodes, boundary nodes, thermal components and the like. The method only focuses on macroscopic parameters, so that the method has the characteristics of less calculation amount, stable calculation process and good real-time performance.
The power system is a large-scale complex system composed of power generation, transmission, distribution, electricity consumption and other equipment and auxiliary control and protection systems thereof, and the dynamic response time of the power system to voltage and frequency changes can be different from a few microseconds, a few milliseconds to a few minutes. The simulation of a dynamic process with such a large time domain range is difficult to be completed at one time, but the dynamic process concerned is simulated in detail according to the simulation requirement, and other processes are simplified approximately.
In the actual simulation process, the simulation of the secondary loop system of the nuclear power plant is generally separated from the simulation of the electric power system, and the actual physical change process cannot be accurately reflected, so that the joint simulation of the secondary loop fluid network system of the nuclear power plant and the electric power system needs to be researched, in the operation process of the nuclear power plant, various power consumption equipment such as an electric valve and an electric pump are switched, and the power consumption equipment is switched to cause the change of the required power, thereby influencing the rotating speed of the turbine equipment of the grid system.
Disclosure of Invention
In order to solve the technical problems, the invention provides a combined simulation method of a nuclear power two-loop fluid system and an electric power system, which comprises the following steps:
modeling a nuclear power two-loop fluid system according to a mass conservation equation, a momentum conservation equation and an energy conservation equation, and modeling a steam turbine generator in the nuclear power two-loop fluid system through an isentropic enthalpy drop model;
modeling the electric power system, defining an interaction interface and a communication mode of the nuclear power two-loop fluid system and the electric power system, and respectively performing single-step simulation on the modeled nuclear power two-loop fluid system and the electric power system and interacting through the interaction interface and the communication mode.
Further, when the flow value is positive, it indicates that the fluid flow direction is the same as the direction specified by the footmark;
when the flow value is negative, it indicates that the direction of fluid flow is opposite to that prescribed by the subscript.
Further, when the power demand of the electric power system is increased, the opening of the steam inlet regulating valve of the steam turbine generator is controlled to be increased through the steam turbine rotating speed controller, so that the rotating speed of the steam turbine generator is increased.
Furthermore, the communication modes are TCP/IP and websocket, and the cooperative simulation of the nuclear power two-loop fluid system and the electric power system is realized through a C/S architecture.
Further, when the modeled nuclear power two-loop fluid system and the power system are subjected to single-step simulation respectively, the same single-step is set.
The invention also provides a nuclear power two-loop fluid system and electric power system joint simulation system, which comprises:
the modeling module is used for modeling the nuclear power two-loop fluid system according to the mass conservation equation, the momentum conservation equation and the energy conservation equation, and modeling the steam turbine generator in the nuclear power two-loop fluid system through the isentropic enthalpy drop model;
the simulation module is used for modeling the electric power system, defining an interaction interface and a communication mode of the nuclear power two-loop fluid system and the electric power system, respectively carrying out single-step simulation on the modeled nuclear power two-loop fluid system and the electric power system, and carrying out interaction through the interaction interface and the communication mode.
Further, when the flow value is positive, it indicates that the fluid flow direction is the same as the direction specified by the footmark;
when the flow value is negative, it indicates that the direction of fluid flow is opposite to that prescribed by the subscript.
Further, when the power demand of the electric power system is increased, the opening of the steam inlet regulating valve of the steam turbine generator is controlled to be increased through the steam turbine rotating speed controller, so that the rotating speed of the steam turbine generator is increased.
Furthermore, the communication modes are TCP/IP and websocket, and the cooperative simulation of the nuclear power two-loop fluid system and the electric power system is realized through a C/S architecture.
Further, when the modeled nuclear power two-loop fluid system and the power system are subjected to single-step simulation respectively, the same single-step is set.
Compared with the prior art, the technical scheme of the invention has the following beneficial effects:
the combined solution of the two-loop fluid network system and the electric power system is realized, and finally, the physical process of completely describing the coupling change between the two-loop fluid network system of the nuclear power device and the electric power system is achieved.
Drawings
FIG. 1 is a schematic modeling diagram of a turbo generator;
FIG. 2 is a turboset enthalpy entropy diagram;
FIG. 3 is a schematic diagram of a turbo generator inlet regulator valve control;
FIG. 4 is a joint simulation schematic;
fig. 5 is a block diagram of the system of the present invention.
Detailed Description
In order to better understand the above technical solutions, the following detailed description will be given with reference to the accompanying drawings and specific embodiments.
The method provided by the invention can be implemented in a terminal environment, wherein the terminal can comprise one or more of the following components: processor, storage medium, and display screen. Wherein the storage medium has stored therein at least one instruction that is loaded and executed by the processor to implement the method described in the embodiments below.
The processor may include one or more processing cores. The processor connects various parts within the overall terminal using various interfaces and lines, performs various functions of the terminal and processes data by executing or executing instructions, programs, code sets, or instruction sets stored in the storage medium, and invoking data stored in the storage medium.
The storage medium may include a random access Memory (Random Access Memory, RAM) or a Read-Only Memory (ROM). The storage medium may be used to store instructions, programs, code sets, or instructions.
The display screen is used for displaying a user interface of each application program.
All subscripts in the formula of the invention are only used for distinguishing parameters and have no practical meaning.
In addition, it will be appreciated by those skilled in the art that the structure of the terminal described above is not limiting and that the terminal may include more or fewer components, or may combine certain components, or a different arrangement of components. For example, the terminal further includes components such as a radio frequency circuit, an input unit, a sensor, an audio circuit, a power supply, and the like, which are not described herein.
Example 1
The invention relates to a combined simulation method of a nuclear power two-loop fluid system and an electric power system, which comprises the following steps: step one: and establishing a simulation model of the two-loop fluid network system of the nuclear power plant and main equipment of the two-loop fluid network system. The fluid network can be mainly abstracted into three parts of boundary, node and streamline, and the establishment of the fluid network system is mainly based on three conservation equations: conservation of mass equation, conservation of momentum equation, conservation of energy equation.
Mass conservation equation:
wherein V is i -volume of node i, m 3 ；
ρ i Average density of node i, kg/m 3 ；
D ij -an association matrix between node i and internal node j;
DE ik -an incidence matrix between node i and pressure boundary node k;
DF im -an incidence matrix between node i and traffic border node m;
G ij -the flow value from node i to node j, kg/s;
GE ik -flow value of node i towards pressure boundary node k, kg/s;
GF im -the flow value of node i towards flow boundary node m, kg/s.
X, Y, Z are the number of internal nodes, pressure boundary nodes, flow boundary nodes, respectively, and t is time.
When the flow value is positive, the flow direction of the fluid is the same as the direction specified by the footmark; when the flow value is negative, it indicates that the direction of fluid flow is opposite to that prescribed by the subscript.
Energy conservation equation:
in the formula, h i -specific enthalpy value of internal node i, kJ/kg;
hE k -specific enthalpy value of pressure boundary node k, kJ/kg;
hF m -specific enthalpy value of flow boundary node m, kJ/kg;
S i -heat dissipation capacity between the internal node i and the environment, kJ/s;
M i is the quality of the ith internal node, h j The specific enthalpy value of the internal node j is the specific enthalpy value of the flow boundary.
Momentum conservation equation:
momentum conservation equation for the flow line between the interiors:
momentum conservation equation for the streamline connected to the pressure boundary:
wherein I is ij ,I ik Flow lines between internal nodes i, j, structural coefficients of flow lines connected to pressure boundaries, mpa·s 2 /kg；
PE k 、P i -pressure boundary node k, pressure value of internal node i, MPa;
hg. HEg-gravity pressure differential across the internal flow line, pressure boundary flow line, MPa;
f ij 、fE ij -resistance pressure drop over the internal flow line, pressure boundary flow line, MPa.
HEg ik Is the gravitational pressure difference between the internal node i and the pressure boundary node k; hg of Hg ij Is the gravity pressure difference between the internal node i and the internal node j; f (f) ij Is the resistance pressure drop between internal node i and internal node; fE (fE) ik Is the resistive pressure drop between the internal node i and the pressure boundary node k.
The modeling schematic diagram of the steam turbine generator is shown in figure 1, an isentropic enthalpy drop model is adopted, the entropy value of steam is considered to be unchanged in the working process of the steam turbine generator, and the steam turbine is shown in figure 2The pressure value of the steam parameter at the inlet of the machine is P in A specific enthalpy value of h in The inlet steam entropy obtained by physical property inquiry is as follows:
S in ＝f(P in ,h in ) (3-31)
the outlet enthalpy value is:
h out ＝f(P out ,S) (3-32)
in the formula, ho ut -turbine outlet enthalpy, kJ;
Po ut turbine outlet pressure, MPa.
S-turbine inlet entropy, kg/S.
The power of the turbine generator is as follows:
W＝η·G·(ho ut -h in ) (3-33)
wherein W is the power of a steam turbine, kW;
η -turbine efficiency.
G-steam flow of steam turbine, kg/s.
In addition, the invention also models the nuclear power two-loop fluid system in another mode, which specifically comprises the following steps:
P gen ＝e gen P th
V control -V gen ＝I control (R control +jωL control )
V gen -V out ＝I gen (R gen +jωL gen )
P load ＝|V out | 2 /Z load
wherein P is th For the thermal power of nuclear reactors, m f For nuclear fuel mass, c f To the specific heat capacity of nuclear fuel, T f Is the fuel temperature, t is the time, ρ f For nuclear fuel density, V f For fuel volume, k in nuclear reactor eff Is an effector, beta is an energy-saving factor, P control For the power of the reactor control system, φ is neutron flux, Σ f For nuclear fuel fission cross-section, Σ a For nuclear fuel absorption cross section, P sec Is the thermal power of the steam generator, h is the heat transfer coefficient,c for coolant mass flow rate cool To specific heat capacity of coolant, T in T for the temperature of the coolant entering the steam generator from the nuclear reactor out For the coolant temperature at the steam generator outlet, P gen For generating power of the generator e gen For the efficiency of the generator, V control For controlling the voltage of the system of the reactor, V gen For the voltage of the generator, I control R is the current of the reactor control system control For the resistance of the reactor control system, +.>In imaginary units, ω is angular frequency, L control Inductance for reactor control system, V out For the output voltage of the power system, I gen R is the current of the generator gen Is the resistance of the generator, L gen Is the inductance of the generator, P load Is the active power of the load, z load Impedance of load of electric power system, Q load For reactive power of the load, +.>Is the complex conjugate of the load current and Im is the imaginary part.
Step two: and establishing a simulation model of the power system. The system mainly comprises a power grid load model of electric equipment such as an electric valve, an electric pump and the like.
P all ＝ΣP i
Wherein P is all -total power demand of the electrical power system;
P i -power demand of each consumer
Wherein P is the pole pair number of the motor;
j, the moment of inertia of the motor;
T e -electromagnetic torque of the motor;
T m -mechanical torque;
ω r is the rotor angular velocity.
Step three: an interactive interface of a nuclear power plant two-loop fluid network system and an electric power system is defined. In the operation process of the nuclear power plant, the two-loop fluid network system mainly transmits generated steam to steam-using equipment such as a steam turbine generator and the like, converts the steam into power required by the steam turbine generator unit, and generates required electric energy under the condition of designing specified steam parameters and steam yield. The rotation speed of the steam turbine generator directly depends on the required power of the electric power system, when the required power of the electric power system is increased, the rotation speed of the steam turbine generator needs to be increased, and then the opening of the steam inlet regulating valve of the steam turbine generator is controlled to be increased through the rotation speed controller of the steam turbine generator, so that the rotation speed of the steam turbine is increased, and the same is true, as shown in fig. 3.
Step four: communication between the nuclear power plant two-circuit fluid network system and the power system simulation is established. Based on TCP/IP and websocket, the collaborative simulation of the two loop system client of the nuclear power device and the power system client is realized through a C/S architecture. As shown in fig. 4.
Step five: and performing joint simulation of the two-loop fluid network of the nuclear power plant and the electric power system. The main process is that firstly, single-step simulation of a flow network system and single-step simulation of an electric power system are respectively carried out, at the moment, the simulation step sizes of the two systems are set to be equal, after the single simulation of the two systems is respectively completed, data exchange between the systems is carried out based on communication and a defined system interface, and then the next step simulation and the combined simulation flow are carried out.
Example 2
As shown in fig. 5, the present invention further provides a combined simulation system of a nuclear power two-loop fluid system and an electric power system, including:
the modeling module is used for modeling the nuclear power two-loop fluid system according to the mass conservation equation, the momentum conservation equation and the energy conservation equation, and modeling the steam turbine generator in the nuclear power two-loop fluid system through the isentropic enthalpy drop model;
the simulation module is used for modeling the electric power system, defining an interaction interface and a communication mode of the nuclear power two-loop fluid system and the electric power system, respectively carrying out single-step simulation on the modeled nuclear power two-loop fluid system and the electric power system, and carrying out interaction through the interaction interface and the communication mode.
Specifically, when the flow value is a positive number, it indicates that the fluid flow direction is the same as the direction specified by the footmark;
when the flow value is negative, it indicates that the direction of fluid flow is opposite to that prescribed by the subscript.
Specifically, when the power demand of the electric power system is increased, the opening of the steam inlet regulating valve of the steam turbine generator is controlled to be increased through the steam turbine rotating speed controller, so that the rotating speed of the steam turbine generator is increased.
Specifically, the communication modes are TCP/IP and websocket, and the cooperative simulation of the nuclear power two-loop fluid system and the electric power system is realized through a C/S architecture.
Specifically, when the modeled nuclear power two-loop fluid system and the power system are subjected to single-step simulation respectively, the same single-step is set.
Example 3
The embodiment of the invention also provides a storage medium which stores a plurality of instructions for realizing the combined simulation method of the nuclear power two-loop fluid system and the electric power system.
Alternatively, in this embodiment, the storage medium may be located in any one of the computer terminals in the computer terminal group in the computer network, or in any one of the mobile terminals in the mobile terminal group.
Alternatively, in the present embodiment, the storage medium is configured to store program code for performing the steps of: modeling a nuclear power two-loop fluid system according to a mass conservation equation, a momentum conservation equation and an energy conservation equation, and modeling a steam turbine generator in the nuclear power two-loop fluid system through an isentropic enthalpy drop model;
modeling the electric power system, defining an interaction interface and a communication mode of the nuclear power two-loop fluid system and the electric power system, and respectively performing single-step simulation on the modeled nuclear power two-loop fluid system and the electric power system and interacting through the interaction interface and the communication mode.
Specifically, when the flow value is a positive number, it indicates that the fluid flow direction is the same as the direction specified by the footmark;
when the flow value is negative, it indicates that the direction of fluid flow is opposite to that prescribed by the subscript.
Specifically, when the power demand of the electric power system is increased, the opening of the steam inlet regulating valve of the steam turbine generator is controlled to be increased through the steam turbine rotating speed controller, so that the rotating speed of the steam turbine generator is increased.
Specifically, the communication modes are TCP/IP and websocket, and the cooperative simulation of the nuclear power two-loop fluid system and the electric power system is realized through a C/S architecture.
Specifically, when the modeled nuclear power two-loop fluid system and the power system are subjected to single-step simulation respectively, the same single-step is set.
Example 4
The embodiment of the invention also provides electronic equipment, which comprises a processor and a storage medium connected with the processor, wherein the storage medium stores a plurality of instructions, and the instructions can be loaded and executed by the processor so that the processor can execute a combined simulation method of a nuclear power two-loop fluid system and an electric power system.
Specifically, the electronic device of the present embodiment may be a computer terminal, and the computer terminal may include: one or more processors, and a storage medium.
The storage medium can be used for storing software programs and modules, such as a combined simulation method of the nuclear power two-loop fluid system and the electric power system in the embodiment of the invention, corresponding program instructions/modules, and the processor executes various functional applications and data processing by running the software programs and the modules stored in the storage medium, so that the combined simulation method of the nuclear power two-loop fluid system and the electric power system is realized. The storage medium may include a high-speed random access storage medium, and may also include a non-volatile storage medium, such as one or more magnetic storage systems, flash memory, or other non-volatile solid-state storage medium. In some examples, the storage medium may further include a storage medium remotely located with respect to the processor, and the remote storage medium may be connected to the terminal through a network. Examples of such networks include, but are not limited to, the internet, intranets, local area networks, mobile communication networks, and combinations thereof.
The processor may invoke the information stored in the storage medium and the application program via the transmission system to perform the steps of: alternatively, in this embodiment, the storage medium may be located in any one of the computer terminals in the computer terminal group in the computer network, or in any one of the mobile terminals in the mobile terminal group.
Alternatively, in the present embodiment, the storage medium is configured to store program code for performing the steps of: modeling a nuclear power two-loop fluid system according to a mass conservation equation, a momentum conservation equation and an energy conservation equation, and modeling a steam turbine generator in the nuclear power two-loop fluid system through an isentropic enthalpy drop model;
modeling the electric power system, defining an interaction interface and a communication mode of the nuclear power two-loop fluid system and the electric power system, and respectively performing single-step simulation on the modeled nuclear power two-loop fluid system and the electric power system and interacting through the interaction interface and the communication mode.
Specifically, when the flow value is a positive number, it indicates that the fluid flow direction is the same as the direction specified by the footmark;
when the flow value is negative, it indicates that the direction of fluid flow is opposite to that prescribed by the subscript.
Specifically, when the power demand of the electric power system is increased, the opening of the steam inlet regulating valve of the steam turbine generator is controlled to be increased through the steam turbine rotating speed controller, so that the rotating speed of the steam turbine generator is increased.
Specifically, the communication modes are TCP/IP and websocket, and the cooperative simulation of the nuclear power two-loop fluid system and the electric power system is realized through a C/S architecture.
Specifically, when the modeled nuclear power two-loop fluid system and the power system are subjected to single-step simulation respectively, the same single-step is set.
The foregoing embodiment numbers of the present invention are merely for the purpose of description, and do not represent the advantages or disadvantages of the embodiments.
In the foregoing embodiments of the present invention, the descriptions of the embodiments are emphasized, and for a portion of this disclosure that is not described in detail in this embodiment, reference is made to the related descriptions of other embodiments.
In the embodiments provided in the present invention, it should be understood that the disclosed technology may be implemented in other manners. The system embodiments described above are merely exemplary, and for example, the division of the units is merely a logic function division, and there may be another division manner in actual implementation, for example, multiple units or components may be combined or integrated into another system, or some features may be omitted or not performed. Alternatively, the coupling or direct coupling or communication connection shown or discussed with each other may be through some interfaces, units or modules, or may be in electrical or other forms.
The units described as separate units may or may not be physically separate, and units shown as units may or may not be physical units, may be located in one place, or may be distributed on a plurality of network units. Some or all of the units may be selected according to actual needs to achieve the purpose of the solution of this embodiment.
In addition, each functional unit in the embodiments of the present invention may be integrated in one processing unit, or each unit may exist alone physically, or two or more units may be integrated in one unit. The integrated units may be implemented in hardware or in software functional units.
The integrated units, if implemented in the form of software functional units and sold or used as stand-alone products, may be stored in a computer readable storage medium. Based on such understanding, the technical solution of the present invention may be embodied essentially or partly in the form of a software product or all or part of the technical solution, which is stored in a storage medium, and includes several instructions for causing a computer device (which may be a personal computer, a server, or a network device, etc.) to perform all or part of the steps of the method according to the embodiments of the present invention. And the aforementioned storage medium includes: a U-disk, a Read-Only Memory (ROM), a random-access Memory (RAM, random Access Memory), a removable hard disk, a magnetic disk, or an optical disk, or the like, which can store program codes.
It is apparent that the above examples are given by way of illustration only and are not limiting of the embodiments. Other variations or modifications of the above teachings will be apparent to those of ordinary skill in the art. It is not necessary here nor is it exhaustive of all embodiments. While still being apparent from variations or modifications that may be made by those skilled in the art are within the scope of the invention.
Claims (10)
1. The combined simulation method of the nuclear power two-loop fluid system and the electric power system is characterized by comprising the following steps of:
modeling a nuclear power two-loop fluid system according to a mass conservation equation, a momentum conservation equation and an energy conservation equation, and modeling a steam turbine generator in the nuclear power two-loop fluid system through an isentropic enthalpy drop model;
modeling the electric power system, defining an interaction interface and a communication mode of the nuclear power two-loop fluid system and the electric power system, and respectively performing single-step simulation on the modeled nuclear power two-loop fluid system and the electric power system and interacting through the interaction interface and the communication mode.
2. The combined simulation method of a nuclear power two-loop fluid system and an electric power system according to claim 1, wherein when the flow value is positive, the flow direction of the fluid is the same as the direction specified by the footmark;
when the flow value is negative, it indicates that the direction of fluid flow is opposite to that prescribed by the subscript.
3. The combined simulation method of a nuclear power two-loop fluid system and an electric power system according to claim 1, wherein when the required power of the electric power system is increased, the opening of a steam inlet regulating valve of the steam turbine generator is controlled to be increased through a steam turbine rotating speed controller, so that the rotating speed of the steam turbine generator is increased.
4. The combined simulation method of the nuclear power two-loop fluid system and the electric power system according to claim 1, wherein the communication mode is TCP/IP and websocket, and the combined simulation of the nuclear power two-loop fluid system and the electric power system is realized through a C/S architecture.
5. The method for joint simulation of a nuclear power two-circuit fluid system and an electric power system according to claim 1, wherein the same single step size is set when the modeled nuclear power two-circuit fluid system and the electric power system are subjected to single step simulation respectively.
6. A nuclear power two-circuit fluid system and electric power system joint simulation system, comprising:
the modeling module is used for modeling the nuclear power two-loop fluid system according to the mass conservation equation, the momentum conservation equation and the energy conservation equation, and modeling the steam turbine generator in the nuclear power two-loop fluid system through the isentropic enthalpy drop model;
the simulation module is used for modeling the electric power system, defining an interaction interface and a communication mode of the nuclear power two-loop fluid system and the electric power system, respectively carrying out single-step simulation on the modeled nuclear power two-loop fluid system and the electric power system, and carrying out interaction through the interaction interface and the communication mode.
7. The combined simulation system of a nuclear power two-loop fluid system and an electric power system according to claim 6, wherein when the flow value is positive, the flow direction of the fluid is the same as the direction specified by the footmark;
when the flow value is negative, it indicates that the direction of fluid flow is opposite to that prescribed by the subscript.
8. The nuclear power two-loop fluid system and electric power system joint simulation system according to claim 6, wherein when the power demand of the electric power system is increased, the opening of the steam inlet regulating valve of the steam turbine generator is controlled to be increased by the steam turbine rotating speed controller, so that the rotating speed of the steam turbine generator is increased.
9. The combined simulation system of the nuclear power two-loop fluid system and the electric power system according to claim 6, wherein the communication modes are TCP/IP and websocket, and the combined simulation of the nuclear power two-loop fluid system and the electric power system is realized through a C/S architecture.
10. The nuclear power two loop fluid system and electric power system joint simulation system of claim 6, wherein the same single step size is set when the modeled nuclear power two loop fluid system and electric power system are single-step simulated, respectively.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311412587.2A CN117763979A (en) | 2023-10-26 | 2023-10-26 | Nuclear power two-loop fluid system and electric power system joint simulation method and system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311412587.2A CN117763979A (en) | 2023-10-26 | 2023-10-26 | Nuclear power two-loop fluid system and electric power system joint simulation method and system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN117763979A true CN117763979A (en) | 2024-03-26 |
Family
ID=90313239
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202311412587.2A Pending CN117763979A (en) | 2023-10-26 | 2023-10-26 | Nuclear power two-loop fluid system and electric power system joint simulation method and system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117763979A (en) |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104794297A (en) * | 2015-04-29 | 2015-07-22 | 国网上海市电力公司电力科学研究院电源技术中心 | Method for eliminating distortion in steam turbine speed regulation system model |
| CN113486608A (en) * | 2021-07-05 | 2021-10-08 | 西安交通大学 | Two-loop modular modeling simulation method for nuclear power system |
| CN115935838A (en) * | 2022-11-14 | 2023-04-07 | 中国船舶重工集团公司第七一九研究所 | Modeling simulation method for two-loop condensate water supply system of nuclear power plant |
-
2023
- 2023-10-26 CN CN202311412587.2A patent/CN117763979A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104794297A (en) * | 2015-04-29 | 2015-07-22 | 国网上海市电力公司电力科学研究院电源技术中心 | Method for eliminating distortion in steam turbine speed regulation system model |
| CN113486608A (en) * | 2021-07-05 | 2021-10-08 | 西安交通大学 | Two-loop modular modeling simulation method for nuclear power system |
| CN115935838A (en) * | 2022-11-14 | 2023-04-07 | 中国船舶重工集团公司第七一九研究所 | Modeling simulation method for two-loop condensate water supply system of nuclear power plant |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Wang et al. | Standardized matrix modeling of multiple energy systems | |
| CN103280821B (en) | Multi-period dynamic reactive power optimization method of intelligent power distribution system | |
| CN110598913B (en) | Optimization method and system for equipment capacity configuration of park comprehensive energy system | |
| CN109711601A (en) | The hot integrated energy system distributed optimization dispatching method of electric-gas-and device | |
| CN108241782B (en) | Mixed transient analysis method and mixed transient analysis system | |
| CN107666155A (en) | System Stochastic Stability Analysis method of providing multiple forms of energy to complement each other based on Markov model | |
| CN110601177B (en) | Economic optimization method for micro-grid containing wind power and photovoltaic power generation | |
| Yang et al. | Bi-level multi-objective optimal design of integrated energy system under low-carbon background | |
| CN110112785B (en) | Comprehensive energy system simplified model design method based on equilibrium transformation theory | |
| CN114492011A (en) | Energy Internet digital twin simulation system and method | |
| CN117763979A (en) | Nuclear power two-loop fluid system and electric power system joint simulation method and system | |
| Du et al. | An optimization framework for dynamic hybrid energy systems | |
| CN113156835A (en) | Modeling simulation method for operation control of electricity-heat comprehensive energy system | |
| CN113258559A (en) | Game optimization method for combined cooling heating and power supply micro-grid group system | |
| CN111724026A (en) | Optimization method for coupling operation of multi-energy network and water distribution network | |
| CN107171329A (en) | A kind of distribution power system load flow calculation method containing new-energy grid-connected | |
| CN109390959B (en) | Storage battery energy storage control method based on virtual synchronous machine technology | |
| CN115936228A (en) | University city comprehensive energy system operation optimization method and device considering distribution network architecture | |
| CN102856922B (en) | Synchronous generator parameter equivalent method for micro-grid connection simulation | |
| CN112713590B (en) | Combined optimization scheduling method for combined cooling, heating and power supply microgrid and active power distribution network considering IDR (Integrated data Rate) | |
| CN113037837B (en) | Intelligent terminal facing comprehensive energy system and based on edge calculation and control method thereof | |
| Tang et al. | Multi rate dynamic hybrid simulation of integrated energy system | |
| CN112202209A (en) | Multi-power-supply advanced coordination control method and system considering communication delay | |
| CN115619145B (en) | Cooperative control method and device for comprehensive energy system and computer equipment | |
| CN206450988U (en) | GTNET interface cards and source net joint real-time emulation system |
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 |