CN110580375A - nuclear power station containment simulation method and system based on two-phase flow model - Google Patents
nuclear power station containment simulation method and system based on two-phase flow model Download PDFInfo
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Abstract
The invention provides a nuclear power station containment simulation method and system based on a two-phase flow model, belonging to the technical field of nuclear power stations; the method comprises the following steps: establishing a safe shell model corresponding to the real safe shell structure; carrying out node division on the internal space of the safety shell model to establish the corresponding relation between nodes and the space; configuring parameters of the safety shell model; determining a mass energy calculation equation of the gas-liquid two-phase fluid in the containment vessel model to establish a two-phase flow model; and establishing a containment simulation model according to the containment model, the corresponding relation between the nodes and the space, the parameters and the two-phase flow model, and simulating the thermodynamic parameters of the gas-liquid two-phase fluid of the real containment under various working conditions in real time through the containment simulation model. According to the invention, by establishing the two-phase flow model and simulating the parameters of the gas-liquid two-phase fluid under various working conditions in real time through the two-phase flow model, the simulated data is more accurate and reliable.
Description
Technical Field
The invention relates to the technical field of nuclear power stations, in particular to a nuclear power station containment simulation method and system based on a two-phase flow model.
Background
The containment vessel is used as the last safety barrier of the nuclear reactor, and in a nuclear leakage state, the radioactive substance can be controlled in the containment vessel and cannot be leaked into the air, so that the harm to the environment and human bodies is prevented.
The method comprises the steps that a dynamic process of thermodynamic parameters such as pressure and temperature in a containment vessel, pit water level and temperature and the like and the influence of ventilation, spraying and the like on the thermodynamic parameters such as pressure and temperature in the containment vessel system after a fault occurs during accidents such as loss of coolant accident (LOCA) of a reactor coolant system of the nuclear power plant, steam pipeline breakage and small flow leakage of a nuclear island auxiliary support system are simulated correctly and in real time by utilizing a nuclear power plant containment vessel analysis model, and can play an important role in accident condition response training, accident analysis, safety verification test and the like of a nuclear power plant operator; the occurrence of safety accidents can be reduced.
However, in the containment analysis model in the prior art, thermodynamic imbalance influence caused by temperature difference of the liquid phase fluid and the gas phase fluid in the containment is not considered, so that the simulated thermodynamic parameters are not accurate enough.
Disclosure of Invention
the invention provides a nuclear power station containment vessel simulation method and system based on a two-phase flow model, aiming at the problem that a simulated thermodynamic parameter is not accurate enough due to the fact that thermodynamic imbalance influence caused by temperature difference of liquid phase fluid and gas phase fluid in a containment vessel is not considered in a containment vessel analysis model in the prior art.
The technical scheme provided by the invention for the technical problem is as follows:
in one aspect of the invention, a nuclear power station containment simulation method based on a two-phase flow model is provided, and the method comprises the following steps:
establishing a safe shell model corresponding to the real safe shell structure;
determining a mass energy calculation equation of the gas-liquid two-phase fluid in the containment vessel model to establish a two-phase flow model;
carrying out node division on a plurality of rooms in the security shell model to establish a corresponding relation between nodes and the rooms; each node is used as a control body;
configuring parameters of the safety shell model;
And establishing a containment simulation model according to the containment model, the corresponding relation between the nodes and the room, the parameters and the two-phase flow model, and simulating the thermodynamic parameters of the gas-liquid two-phase fluid of the real containment under various working conditions in real time through the containment simulation model.
further, the mass energy calculation equation comprises a gas-liquid mass energy conservation equation, a gas-liquid momentum conservation equation and a gas-liquid phase mass energy heat transfer equation, and the gas-liquid mass energy conservation equation, the gas-liquid momentum conservation equation and the gas-liquid phase mass energy heat transfer equation are used for calculating thermodynamic parameters of gas-liquid two-phase fluid under various working conditions in real time.
Further, the gas-liquid mass-energy conservation equation comprises:
a mixed gas phase mass conservation equation for controlling inflow, outflow and mass conservation of a gas phase space in each of the control bodies;
a liquid phase mass conservation equation for controlling the inflow, outflow and mass conservation of the liquid phase space in each of the control bodies;
A mixed gas phase energy conservation equation for controlling the energy conservation released and absorbed by the gas phase space in each of the control gases; and a process for the preparation of a coating,
and a liquid phase energy conservation equation for controlling the energy conservation released and absorbed by the liquid phase space in each of the control bodies.
further, the specific implementation of node division on the internal space of the safety shell model is as follows: dividing a plurality of rooms in the safety shell model into different nodes according to a real safety shell heat imbalance principle, and establishing a corresponding relation between the nodes and the rooms; each of the nodes acts as a control entity.
Further, the specific implementation of configuring the parameters of the secure shell model is as follows: configuring the parameters of each control body by combining the energy released by each device in the real containment vessel under various working conditions, the geometric data of the real containment vessel, the environment heat absorption factors and the corresponding relation between the control bodies and the rooms;
And the interface configuration of the safety shell model and each process system model of the nuclear power station enables the quality parameters and the energy parameters of each process system model of the nuclear power station to be transmitted to the safety shell model in real time so as to realize the calculation of the gas-liquid two-phase fluid thermodynamic parameters under various working conditions.
in another aspect of the present invention, a nuclear power plant containment simulation system based on a two-phase flow model is provided, which includes:
The containment model establishing module is used for establishing a containment model corresponding to the real containment structure;
The two-phase flow model establishing module is connected with the containment vessel model establishing module and used for determining a mass-energy calculation equation of gas-liquid two-phase fluid in the containment vessel model so as to establish a two-phase flow model;
the node division module is connected with the containment model building module and is used for carrying out node division on a plurality of rooms in the containment model so as to build a corresponding relation between nodes and the rooms; each node is used as a control body;
The parameter configuration module is connected with the containment model establishing module and is used for configuring parameters of the containment model;
and the parameter real-time simulation module is connected with the containment model establishing module, the two-phase flow model establishing module, the node dividing module and the parameter configuration module, and is used for establishing a containment simulation model according to the containment model, the corresponding relation between the nodes and the room, the parameters and the two-phase flow model, and simulating the thermodynamic parameters of the gas-liquid two-phase fluid of the real containment under various working conditions in real time through the containment simulation model.
Further, the mass energy calculation equation comprises a gas-liquid mass energy conservation equation, a gas-liquid momentum conservation equation and a gas-liquid phase mass energy heat transfer equation, and the gas-liquid mass energy conservation equation, the gas-liquid momentum conservation equation and the gas-liquid phase mass energy heat transfer equation are used for calculating thermodynamic parameters of gas-liquid two-phase fluid under various working conditions in real time.
Further, the gas-liquid mass-energy conservation equation comprises:
a mixed gas phase mass conservation equation for controlling inflow, outflow and mass conservation of a gas phase space in each of the control bodies;
a liquid phase mass conservation equation for controlling the inflow, outflow and mass conservation of the liquid phase space in each of the control bodies;
A mixed gas phase energy conservation equation for controlling the energy conservation released and absorbed by the gas phase space in each of the control gases; and a process for the preparation of a coating,
and a liquid phase energy conservation equation for controlling the energy conservation released and absorbed by the liquid phase space in each of the control bodies.
further, the node division module is specifically configured to divide a plurality of rooms in the containment shell model into different nodes according to a real containment shell heat imbalance principle, and establish a correspondence between the nodes and the rooms; each of the nodes acts as a control entity.
Further, the parameter configuration module is specifically configured to configure the parameters of each control body in combination with the energy released by each device in the real containment vessel under various working conditions, the geometric data of the real containment vessel, the environmental endothermic factors, and the corresponding relationship between the control body and the room;
and the interface configuration is used for the safety shell model and each process system model of the nuclear power station, so that the quality parameters and the energy parameters of each process system model of the nuclear power station can be transmitted to the safety shell model in real time, and the calculation of the gas-liquid two-phase fluid thermodynamic parameters under various working conditions is realized.
the technical scheme provided by the embodiment of the invention has the following beneficial effects:
By establishing a two-phase flow model and simulating thermodynamic parameters of gas-liquid two-phase fluid under various working conditions in real time through the two-phase flow model, the thermodynamic parameters simulated through the containment simulation model are more accurate and reliable; meanwhile, a plurality of rooms in the containment model are subjected to node division, and the divided rooms have the characteristic that the size of the nodes is insensitive, so that the method is particularly suitable for the requirements of real-time simulators of various possible transients which are predicted by using a node scheme; according to the invention, the nuclear power station containment simulation method based on the improved two-phase flow model is used for configuring the parameters of the containment model, so that the modeling efficiency is improved, and the model debugging difficulty is reduced.
drawings
FIG. 1 is a flow chart of a nuclear power plant containment simulation method based on a two-phase flow model according to an embodiment of the present invention;
Fig. 2 is a diagram of a correspondence relationship between a control body and a room according to an embodiment of the present invention;
FIG. 3 is a gas phase flow tuning diagram of a flow channel provided by an embodiment of the invention;
FIG. 4 is a diagram illustrating exemplary configuration of control parameters according to an embodiment of the present invention;
FIG. 5 is a block diagram of a nuclear power plant containment simulation system based on a two-phase flow model according to an embodiment of the present invention.
Detailed Description
The problem that simulated thermodynamic parameters are not accurate enough is solved in the prior art because the influence of thermodynamic imbalance caused by the temperature difference of liquid phase fluid and vapor phase fluid in the containment is not considered in a containment analysis model. In order to solve the problems, the invention aims to provide a nuclear power station containment simulation method and system based on a two-phase flow model, and the core idea is as follows: by establishing a two-phase flow model and simulating thermodynamic parameters of gas-liquid two-phase fluid under various working conditions in real time through the two-phase flow model, the thermodynamic parameters simulated through the containment simulation model are more accurate and reliable; meanwhile, a plurality of rooms in the containment model are subjected to node division, and the divided rooms have the characteristic that the size of the nodes is insensitive, so that the method is particularly suitable for the requirements of real-time simulators of various possible transients which are predicted by using a node scheme; according to the invention, the nuclear power station containment simulation method based on the improved two-phase flow model is used for configuring the parameters of the containment model, so that the modeling efficiency is improved, and the model debugging difficulty is reduced.
in order to make the objects, technical solutions and advantages of the present invention more apparent, embodiments of the present invention will be described in detail with reference to the accompanying drawings.
Referring to fig. 1, a first embodiment of the present invention provides a nuclear power plant containment simulation method based on a two-phase flow model, including the following steps:
Step 1, establishing a safety shell model corresponding to a real safety shell structure;
Step 2, determining a mass energy calculation equation of the gas-liquid two-phase fluid in the containment vessel model to establish a two-phase flow model;
Step 3, carrying out node division on a plurality of rooms in the safety shell model to establish a corresponding relation between the nodes and the rooms;
step 4, configuring parameters of the safety shell model;
And 5, establishing a containment simulation model according to the containment model, the corresponding relation between the nodes and the space, the parameters and the two-phase flow model, and simulating the thermodynamic parameters of the gas-liquid two-phase fluid of the real containment under various working conditions in real time through the containment simulation model. In this embodiment, the thermodynamic parameters include temperature, pressure, enthalpy, and flow rate.
in this embodiment, the containment structure is a solid device contained in a containment, and step 1 is used to complete establishment of a model corresponding to the solid device in the real containment in a containment model. And the step 2 is used for establishing a two-phase flow model, wherein the input quantity of the two-phase flow model is the quality parameter and the energy parameter of each process system model of the nuclear power station, and the output quantity of the two-phase flow model is the thermodynamic parameter of the gas-liquid two-phase fluid. Because the data in the containment vessel is numerous, in order to simplify the calculation process and enable the thermodynamic parameters calculated by the two-phase flow model to be more accurate and reliable, a plurality of rooms in the containment vessel model need to be divided into nodes to establish the corresponding relation between the nodes and the rooms, each node is used as a control body (corresponding to the step 3), and when the calculation is performed through the two-phase flow model, the control body is directly used as a unit, and the quality parameters and the energy parameters of each control body are substituted into the two-phase flow model for calculation to obtain the thermodynamic parameters of the control body. In addition, in the step 1, only the establishment of the model corresponding to the entity equipment in the real containment in the containment model is completed, and parameters such as energy, geometric data, environmental endothermic factors and the like released by each equipment model are not configured, so that the nuclear power station containment simulation method further comprises the step 4 of configuring the parameters of the containment model; after the parameters are configured, the specific numerical values of the known parameters in the mass-energy calculation equation of the two-phase flow model are correspondingly obtained, so that the thermodynamic parameters under various working conditions can be smoothly solved through the mass-energy calculation equation.
further, the mass-energy calculation equation comprises a gas-liquid mass-energy conservation equation, which comprises: a mixed gas phase mass conservation equation, a liquid phase mass conservation equation, a mixed gas phase energy conservation equation and a liquid phase energy conservation equation. In the embodiment, the gas phase and the liquid phase are respectively provided with a mass and energy conservation equation, and compared with a model using an equation, the mass and energy conservation equation is more stable in structure and numerical calculation and is easier to process mass and energy exchange terms passing through a two-phase interface; the mass exchange among phases and the energy exchange generated by the mass exchange are the most important phenomena in unbalanced two-phase flow, so that the two-phase flow model provided by the application can better deal with the problem of thermodynamic imbalance of liquid phase fluid and gas phase fluid in the containment.
furthermore, the mass-energy calculation equation also comprises a gas-liquid momentum conservation equation, and the momentum change process of the two-phase flow is predicted by adopting a mixed momentum conservation equation, so that the mass-energy calculation equation has the advantages of good numerical calculation stability and high speed. The mass-energy calculation equation also comprises a gas-liquid mass-energy conservation equation, and the gas-liquid momentum conservation equation and the gas-liquid phase mass-energy heat transfer equation are used for calculating thermodynamic parameters of gas-liquid two-phase fluid under various working conditions in real time according to mass parameters and energy parameters transmitted by each process system model of the nuclear power station. And the transmission of the quality parameters and the energy parameters of each process system model of the nuclear power station is realized by connecting the safety shell model with corresponding interfaces on each process system model of the nuclear power station.
Specifically, the calculation method of the two-phase flow model comprises the following steps:
a) The mass conservation equation of the mixed gas phase represents the conservation relation of inflow and outflow in each control body and the gas phase space mass;
In the formula, t istime; x is the xth control; alpha is alpha1＝V1v is the void fraction, V1、V2V is gas phase, liquid phase and volume of control body respectively, V ═ V1+V2；ρ1is the gas phase density; u is the working medium flow rate; f. of1Is the gas phase fluid flow into the control body; gamma-shaped21Is the mass transfer (evaporation and condensation) between the phases, gammadfAnd Γbgrepresenting droplets falling into the liquid and bubbles entering the vapor/gas, respectively.
b) the liquid phase mass conservation equation represents the conservation relation of inflow and outflow in each control body and the liquid phase space mass;
In the formula, alpha2＝V2V is the liquid content; rho2Is the liquid phase density; f. of2Is the liquid phase fluid flow out of the control body;
Wherein alpha is1+α21-formula 3
c) The conservation of energy of the mixed gas phase represents the conservation relation of the released and absorbed energy of the gas phase space in each control gas;
in the formula, h1Is a vapor phase enthalpy value; p is the control body pressure;is the enthalpy value of the working medium flowing into the control body; q. q.s1Is a gas phase heat transfer; q12Is the heat transfer between the non-condensable gas and the liquid;Is gas phase interface heat transfer;is the specific enthalpy of the gas phase fluid or itsaturated steam (h) at its partial steam pressureg sat) Liquid (h)f sat) An enthalpy value; h isdis the droplet enthalpy; h isbis the bubble enthalpy value;
d) Liquid phase energy conservation, which represents the conservation relation of the energy released and absorbed by the liquid phase space in each control body;
In the formula, h2Is the liquid phase enthalpy;is the enthalpy value of the working medium flowing out of the control body;Liquid phase interface heat transfer;Is the specific enthalpy of the liquid phase fluid or its saturated steam (h) at its steam partial pressureg sat) Liquid (h)f sat) An enthalpy value;
e) momentum equation (i.e., gas-liquid momentum conservation equation): it represents the conservation relation of the momentum of the mixture of gas and liquid phases in each control gas;
a is the control body admittance; z is a node elevation; sij1 denotes the direction of flow from node i to j, sijwith-1 indicating a flow direction from node j to i.
f) mass and heat transfer equation between phases (i.e. gas-liquid mass energy conservation equation):
The mass and energy exchange between phases is the dominant phenomenon in thermodynamically unbalanced two-phase flow. The heat exchange is determined by the temperature gradient between each phase and the phase interface, which is equal to the saturation temperature at the partial pressure, and the phases may be either overheated or underoverheated. Thus, the heat exchange direction may be from the phase boundary into each phase or out of each phase.
gas and liquid phase interface heat transferandand interfacial interphase heat transfer, the sum of which is zero:
Heat transfer at vertically layered vapor and liquid phase interfaceAnd
in the formula, Ps1is the partial pressure of the steam in the mixed gas phase,the saturation temperature of the steam and bubbles at the partial pressure of the steam; t is1and T2Respectively representing the temperature of the gas and liquid phases；the heat transfer coefficients of the vapor and liquid-phase interfaces, respectively. After combining equations 9-11, interfacial phase mass transfer is as follows:
Direct heat transfer between non-condensable gases and liquids:
This equation uses the Dalton (Dalton) rule (p ═ p)sg+pn) Where p isnis the non-condensable gas pressure. Assuming that the temperature of the non-condensable gas in the gas phase is the same as the temperature of the steam, i.e. Tng＝Tsg＝T1. Subscript n represents the non-condensable phase component and subscript s represents the vapor component).
The mass of the droplets falling into the liquid and the bubbles entering the vapor/gas in the mass and energy equation can be calculated by the following simplified equation:
In the formula of alphad、αbthe void fraction of the droplets and bubbles, respectively, is ρd、ρbThe density of the fog drops and the density of the bubbles respectively, L is the liquid level of the control body, H is the height of the control body, delta t is the model time step length, udand ubMean velocities of mist droplets and bubbles are indicated, respectively.
The mass-energy calculation equation and the gas-liquid momentum conservation equation provided by the embodiment are established by adopting a drift flow concept, and are insensitive to the size of the node when the system is subjected to node processing, so that the method is particularly suitable for the requirement of a real-time simulator for predicting various possible transient states by using a node scheme; the complete two-fluid model cannot use a coarser node partitioning scheme; therefore, the method and the device have the advantages that the internal space of the safety shell model is subjected to node division according to the principle of thermal imbalance; that is, the specific implementation of node division for multiple rooms in the security shell model in the present application is as follows: dividing a plurality of rooms in the safety shell model into different nodes according to a real safety shell heat imbalance principle, and establishing a corresponding relation between the nodes and the rooms; each of the nodes acts as a control entity. The real containment comprises a plurality of rooms, wherein part of the rooms are communicated with one another through channels, and the heat balance parameters of the rooms communicated through the channels are the same or similar; after the division, a plurality of rooms which are mutually communicated and have the same or similar heat balance parameters are used as a control body, so that the control body is used as a unit to be substituted into a mass energy calculation equation for calculation, the calculation program can be effectively simplified, and the calculation result is accurate and reliable.
the basic components established by the safety shell model comprise the control body, the flow channel, the thermal structure, the equipment and the boundary conditions. In the embodiment, 23 control bodies are divided into the whole safety shell model, and the corresponding relation between the control bodies (nodes) and a plurality of rooms in the safety shell is shown in table 1; the 3 loops of a loop and their associated equipment are each divided into three different control volumes 5, 6 and 7 to simulate the non-uniform processes that exist in the area under accident conditions.
table 1 containment model node and room corresponding relation table
each containment space number in the table 1 corresponds to one room, and a plurality of rooms in the containment are subjected to node division according to the containment space correlation; the spatial correlation is that the flow channels between the rooms are communicated, and the heat balance parameters of a plurality of rooms communicated through the flow channels are the same or similar; therefore, the present application divides a plurality of rooms, which are communicated with each other through a passage, into one control body so that the heat balance parameters of each control body are the same or similar. Fig. 2 shows the correspondence relationship between the control body 11, the control bodies 0 to 348, the control body 15, the control body 12, the control body 17, the control body 13, the control body 16 to 2, and the control body 10 to 3 and the room, specifically, the control body 11 includes rooms R311, R312, R313, R411, R412, R413, R511, R512, R611, R612; the controller 12 includes rooms R321, R322, R323, R421, R422, R423, R521, R522, R621, R622; the control body 13 includes rooms R331, R332, R333, R431, R432, R433.R531, R532, R631, R632; the control body 15 includes rooms R341, R441, R541, R641, R623; the control body 17 includes rooms R344, R444, R544, R644; the control bodies 0-348 include rooms R248, R242, R348; the control body 10-3 includes rooms R310, R320, R345, R346, R330, R410, R420, R430; the control body 16-2 includes rooms R347, R447.
Further, the specific implementation of configuring the parameters of the secure shell model is as follows: configuring the parameters of each control body by combining the energy released by each device in the real containment vessel under various working conditions, the geometric data of the real containment vessel, the environment heat absorption factors and the corresponding relation between the control bodies and the rooms;
And the interface configuration of the safety shell model and each process system model of the nuclear power station enables the quality parameters and the energy parameters of each process system model of the nuclear power station to be transmitted to the safety shell model in real time so as to realize the calculation of the gas-liquid two-phase fluid thermodynamic parameters under various working conditions.
In this embodiment, the specific implementation of controlling the configuration of the body heat balance parameter includes: in order to ensure the simulation rationality of atmospheric pressure and temperature in the containment under various shutdown and full power working conditions, aiming at the heat flux density released by a loop model and relevant containment data, taking a certain CPR1000 nuclear power station in China as an example, the heat distribution condition of a model object is as follows: reach (REACTOR exotherm) 118 kw; PRZR (potentiostat exotherm) ═ 84 kw; SG1-3 (steam generator) ═ 308kw × 3; the simplifying assumption of environmental heat absorption is mainly focused on the dome and the main space, and the heat capacity is simplified to 6kw by considering the respective mentioned diameter, height, area, density; ground is 3.2 kw; EVR system 680kw 2; EVC system 30kw 2.
In this embodiment, the specific implementation of the configuration of other parameters of the control entity includes: the height, volume and flow setting of the rooms and flow channels communicating the rooms are further verified by combining geometric data of the rooms of the containment factory building, the node volume is set to be a net free volume, the flow channel volume and the node volume are combined, and a single equipment thermal structure, a heat absorption wall and a safety shell wall and environment heat exchange structure in each node are simplified. FIG. 4 shows an example of control body parameter configuration;
In fig. 4, parameters of the wall that absorbs heat are configured, specifically, parameters such as the shape (flat plate or cylinder), the surface condition (vertical or horizontal), the surface area, the net surface area, the material and the thickness of each wall are configured; for example, the wall body 1RX41404VB/01 is provided with a flat plate shape, a vertical surface condition and a surface area of 24.34m2Net surface area of 4.94m2The thickness was 0.50 m. Parameters such as bottom elevation, top elevation, building volume, equipment volume, free volume and the like of each room are configured; for the room R311, the floor height is 4.65m, the roof height is 8.00m, and the building volume is 99.03m3the volume of the apparatus comprises 0m30m of pipe (2)3And 4.01m3with a free volume of 95.02m3. Parameters such as building area, equipment area, circulation area, elevation and length of the circulating cavity are configured; for example, for a cavity of 33874/11468, the building area is 0.02m2The equipment area is 0m2a flow area of 0.02m2the elevation was 7.07m and the length was 1 m.
in this embodiment, the containment model is connected to each process system model of the nuclear power plant, so that the quality parameters and the energy parameters of each process system model of the nuclear power plant can be transmitted to the containment model in real time to realize thermodynamic parameter calculation of the containment model under various working conditions, and an interface configuration method for the process system model of the nuclear power plant is provided as follows: comprises that
a) Establishing atmosphere monitoring in an ETY shell, and performing a small air volume cleaning pipeline on the atmosphere of the containment;
b) Establishing an EAS spray condensing pipeline for relieving the LOCA or steam pipeline rupture accident in the containment;
c) establishing a ventilation line during an EBA shutdown;
d) Establishing an EVC pit ventilation pipeline;
e) Establishing an EVR for taking away heat exchange pipelines released by equipment in a reactor plant and setting gas phase flow under normal working conditions, such as the gas phase flow parameter setting under the normal working conditions of a containment plant shown in FIG. 2;
f) Establishing an accident condition influence system model caused by a breach;
g) Establishing an RCP-TH thermal hydraulic model, which comprises a steam pipeline, a water supply pipeline, a primary loop cold and hot section, a voltage stabilizer surge pipe and a pressure relief box;
h) establishing a downward discharging pipeline and an upward charging pipeline (in front of and behind a heat exchanger) of the RCV system;
i) establishing a RIS safety injection water tank broken port and a safety injection cold section hot section pipeline broken port;
j) and establishing pipelines before and after the RRA heat exchanger and before and after the pump.
by establishing material energy exchange interface configuration of a safety shell model and each process system model of the nuclear power station, the safety shell model is closer to a real containment, and thermodynamic parameters simulated by a containment simulation model are more accurate and reliable. Referring to fig. 3, fig. 3 is a gas phase flow parameter setting of a containment factory building and an EVR system under normal working conditions, that is, the flow of a channel connecting a room in a containment model and a room in the EVR system is set, small boxes in fig. 3 correspond to room numbers, a gas phase flow of a corresponding flow channel is marked on a line segment between the small boxes, and a plurality of small box numbers are aggregated into a control body; specifically, the flow rate of the gas phase between the room 247 and the room 211 is 2000, the flow rate of the gas phase between the room 212 and the room 213 is 1600, the flow rate of the gas phase between the room 213 and the room 247 is 2800, the flow rate of the gas phase between the room 231 and the room 247 is 1600, and the flow rate of the gas phase between the room 233 and the room 247 is 1700. Meanwhile, the corresponding relationship between the rooms and the control bodies can also be seen in combination with fig. 3, for example, the room 247, the room 211, the room 212, the room 213, the room 231, the room 232 and the room 233 which are communicated through the flow channels are divided into the same control body; referring to fig. 4, it can be seen that the control body corresponds to the control body 06.
In the embodiment, by establishing the two-phase flow model and simulating thermodynamic parameters of the gas-liquid two-phase fluid under various working conditions in real time through the two-phase flow model, the thermodynamic parameters simulated through the containment simulation model are more accurate and reliable; meanwhile, the internal space of the safety shell model is divided into nodes, and the divided internal space has the characteristic of insensitive size of the nodes, so that the method is particularly suitable for the requirements of real-time simulators of various possible transients which are predicted by using a node scheme; according to the invention, the nuclear power station containment simulation method based on the improved two-phase flow model is used for configuring the parameters of the containment model, so that the modeling efficiency is improved, and the model debugging difficulty is reduced.
In a second embodiment, a two-phase flow model nuclear power plant containment simulation system, referring to fig. 5, includes:
The containment model building module 1 is used for building a containment model corresponding to a real containment structure;
The two-phase flow model establishing module 2 is connected with the containment model establishing module 1 and is used for determining a mass-energy calculation equation of gas-liquid two-phase fluid in the containment model so as to establish a two-phase flow model;
The node division module 3 is connected with the containment model building module 1 and is used for carrying out node division on a plurality of rooms in the containment model so as to build a corresponding relation between nodes and the rooms; each node is used as a control body;
A parameter configuration module 4, configured to configure parameters of the containment model;
and the parameter real-time simulation module 5 is connected with the containment vessel model building module 1, the two-phase flow model building module 2, the node dividing module 3 and the parameter configuration module 4, and is used for building a containment vessel simulation model according to the containment vessel model, the corresponding relation between the nodes and the room, the parameters and the two-phase flow model, and simulating thermodynamic parameters of a gas-liquid two-phase fluid of a real containment vessel under various working conditions in real time through the containment vessel simulation model.
further, the mass energy calculation equation comprises a gas-liquid mass energy conservation equation, a gas-liquid momentum conservation equation and a gas-liquid phase mass energy heat transfer equation, and the gas-liquid mass energy conservation equation, the gas-liquid momentum conservation equation and the gas-liquid phase mass energy heat transfer equation are used for calculating thermodynamic parameters of gas-liquid two-phase fluid under various working conditions in real time.
further, the gas-liquid mass-energy conservation equation comprises:
a mixed gas phase mass conservation equation for controlling inflow, outflow and mass conservation of a gas phase space in each of the control bodies;
a liquid phase mass conservation equation for controlling the inflow, outflow and mass conservation of the liquid phase space in each of the control bodies;
A mixed gas phase energy conservation equation for controlling the energy conservation released and absorbed by the gas phase space in each of the control gases; and a process for the preparation of a coating,
And a liquid phase energy conservation equation for controlling the energy conservation released and absorbed by the liquid phase space in each of the control bodies.
further, the node dividing module 3 is specifically configured to divide a plurality of rooms in the containment model into different nodes according to a principle that the heat of the containment is unbalanced, and establish a correspondence between the nodes and the rooms; each of the nodes acts as a control entity.
Further, the parameter configuration module 4 is specifically configured to configure the parameter of each control body in combination with the energy released by the containment vessel, the geometric data of the real containment vessel, the environmental endothermic factor, and the corresponding relationship between the control body and the room according to the working states of different devices in the real containment vessel;
And the interface configuration is used for the safety shell model and each process system model of the nuclear power station, so that the quality parameters and the energy parameters of each process system model of the nuclear power station can be transmitted to the safety shell model in real time, and the calculation of the gas-liquid two-phase fluid thermodynamic parameters under various working conditions is realized.
According to the invention, by establishing the two-phase flow model and simulating the parameters of the gas-liquid two-phase fluid under various working conditions in real time through the two-phase flow model, the thermodynamic parameters simulated through the containment simulation model are more accurate and reliable; meanwhile, the internal space of the safety shell model is divided into nodes, and the divided internal space has the characteristic of insensitive size of the nodes, so that the method is particularly suitable for the requirements of real-time simulators of various possible transients which are predicted by using a node scheme; according to the invention, the nuclear power station containment simulation method based on the improved two-phase flow model is used for configuring the parameters of the containment model, so that the modeling efficiency is improved, and the model debugging difficulty is reduced.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents, improvements and the like that fall within the spirit and principle of the present invention are intended to be included therein.
Claims (10)
1. a nuclear power station containment simulation method based on a two-phase flow model is characterized by comprising the following steps:
Establishing a safe shell model corresponding to the real safe shell structure;
determining a mass energy calculation equation of the gas-liquid two-phase fluid in the containment vessel model to establish a two-phase flow model;
carrying out node division on a plurality of rooms in the security shell model to establish a corresponding relation between nodes and the rooms; each node is used as a control body;
Configuring parameters of the safety shell model;
And establishing a containment simulation model according to the containment model, the corresponding relation between the nodes and the room, the parameters and the two-phase flow model, and simulating the thermodynamic parameters of the gas-liquid two-phase fluid of the real containment under various working conditions in real time through the containment simulation model.
2. The two-phase flow model-based nuclear power station containment simulation method according to claim 1, wherein the mass energy calculation equations comprise a gas-liquid mass energy conservation equation, a gas-liquid momentum conservation equation and a gas-liquid phase mass energy heat transfer equation, and the gas-liquid mass energy conservation equation, the gas-liquid momentum conservation equation and the gas-liquid phase mass energy heat transfer equation are used for calculating thermodynamic parameters of gas-liquid two-phase fluid under various working conditions in real time.
3. the two-phase flow model-based nuclear power plant containment simulation method according to claim 2, wherein the gas-liquid mass-energy conservation equation comprises:
A mixed gas phase mass conservation equation for controlling inflow, outflow and mass conservation of a gas phase space in each of the control bodies;
a liquid phase mass conservation equation for controlling the inflow, outflow and mass conservation of the liquid phase space in each of the control bodies;
A mixed gas phase energy conservation equation for controlling the energy conservation released and absorbed by the gas phase space in each of the control gases; and a process for the preparation of a coating,
And a liquid phase energy conservation equation for controlling the energy conservation released and absorbed by the liquid phase space in each of the control bodies.
4. the nuclear power plant containment simulation method based on the two-phase flow model according to claim 1, wherein the node division of the internal space of the containment model is realized by: dividing a plurality of rooms in the safety shell model into different nodes according to a real safety shell heat imbalance principle, and establishing a corresponding relation between the nodes and the rooms; each of the nodes acts as a control entity.
5. The two-phase flow model-based nuclear power plant containment simulation method according to claim 4, wherein the parameters of the containment model are configured by:
configuring the parameters of each control body by combining the energy released by each device in the real containment vessel under various working conditions, the geometric data of the real containment vessel, the environment heat absorption factors and the corresponding relation between the control bodies and the rooms;
And the interface configuration of the safety shell model and each process system model of the nuclear power station enables the quality parameters and the energy parameters of each process system model of the nuclear power station to be transmitted to the safety shell model in real time so as to realize the calculation of the gas-liquid two-phase fluid thermodynamic parameters under various working conditions.
6. A nuclear power station containment simulation system based on a two-phase flow model is characterized by comprising:
the safety shell model building module (1) is used for building a safety shell model corresponding to a real safety shell structure;
The two-phase flow model establishing module (2) is connected with the containment vessel model establishing module (1) and is used for determining a mass-energy calculation equation of gas-liquid two-phase fluid in the containment vessel model so as to establish a two-phase flow model;
the node division module (3) is connected with the containment model building module (1) and is used for carrying out node division on a plurality of rooms in the containment model so as to build the corresponding relation between nodes and the rooms; each node is used as a control body;
The parameter configuration module (4) is connected with the containment model establishing module (1) and is used for configuring parameters of the containment model; and
the parameter real-time simulation module (5) is connected with the containment model building module (1), the two-phase flow model building module (2), the node dividing module (3) and the parameter configuration module (4) and is used for building a containment simulation model according to the containment model, the corresponding relation between the nodes and the room, the parameters and the two-phase flow model and simulating the thermodynamic parameters of the gas-liquid two-phase fluid of the real containment under various working conditions in real time through the containment simulation model.
7. the two-phase flow model-based nuclear power station containment simulation system according to claim 6, wherein the mass-energy calculation equations comprise a gas-liquid mass-energy conservation equation, a gas-liquid momentum conservation equation and a gas-liquid phase mass-energy heat transfer equation, and the gas-liquid mass-energy conservation equation, the gas-liquid momentum conservation equation and the gas-liquid phase mass-energy heat transfer equation are used for calculating thermodynamic parameters of gas-liquid two-phase fluid under various working conditions in real time.
8. the two-phase flow model-based nuclear power plant containment simulation system according to claim 7, wherein the gas-liquid mass-energy conservation equation comprises:
a mixed gas phase mass conservation equation for controlling inflow, outflow and mass conservation of a gas phase space in each of the control bodies;
a liquid phase mass conservation equation for controlling the inflow, outflow and mass conservation of the liquid phase space in each of the control bodies;
A mixed gas phase energy conservation equation for controlling the energy conservation released and absorbed by the gas phase space in each of the control gases; and a process for the preparation of a coating,
And a liquid phase energy conservation equation for controlling the energy conservation released and absorbed by the liquid phase space in each of the control bodies.
9. The nuclear power plant containment simulation system based on a two-phase flow model according to claim 6, wherein the node dividing module (3) is specifically configured to divide a plurality of rooms in the containment model into different nodes according to a real containment heat imbalance principle, and establish a correspondence relationship between the nodes and the rooms; each of the nodes acts as a control entity.
10. The nuclear power plant containment simulation system based on a two-phase flow model according to claim 9, wherein the parameter configuration module (4) is specifically configured to configure the parameters of each control body in combination with the energy released by each device in the real containment under various working conditions, the geometric data of the real containment, the environmental endothermic factors, and the corresponding relationship between the control body and the room;
And the interface configuration is used for the safety shell model and each process system model of the nuclear power station, so that the quality parameters and the energy parameters of each process model of the nuclear power station can be transmitted to the safety shell model in real time, and the calculation of the gas-liquid two-phase fluid thermodynamic parameters under various working conditions is realized.
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