CN116206783A

CN116206783A - Simulation system for thermal hydraulic test of nuclear reactor

Info

Publication number: CN116206783A
Application number: CN202310120036.2A
Authority: CN
Inventors: 黄彦平; 周慧辉; 徐建军; 唐瑜; 谢峰; 谢添舟; 彭劲枫; 谭曙时; 昝元峰
Original assignee: Nuclear Power Institute of China
Current assignee: Nuclear Power Institute of China
Priority date: 2023-02-14
Filing date: 2023-02-14
Publication date: 2023-06-02
Anticipated expiration: 2043-02-14
Also published as: CN116206783B

Abstract

The application provides a simulation system for a nuclear reactor thermal hydraulic test, which comprises a test simulation subsystem and an environment simulation subsystem, wherein the test simulation subsystem comprises a water supply module, a flow detection module and a reactor simulation module, the reactor simulation module comprises a simulation reactor and a heat exchange unit, at least part of the heat exchange unit is arranged in the simulation reactor, the water supply module is connected with the simulation reactor through the flow detection module, and the water supply module is connected with the heat exchange unit through the flow detection module; the environment simulation subsystem comprises a driving module and a workbench connected with the driving module, the test simulation subsystem is arranged on the workbench, and the driving module is used for driving the workbench so as to simulate the state of the thermal hydraulic test device when various degrees of freedom are generated under the action of transient external force, and the actual flow change between the water supply module and the reactor simulation module can be detected through the flow detection module without calculation, so that the reliability of the thermal hydraulic characteristic research is improved.

Description

Simulation system for thermal hydraulic test of nuclear reactor

Technical Field

The application belongs to the technical field of nuclear engineering, and particularly relates to a simulation system for a nuclear reactor thermal hydraulic test.

Background

The nuclear reactor is a device for realizing nuclear energy utilization by maintaining a controllable self-sustaining chain type nuclear fission reaction, and has the characteristics of concentrated energy, low fuel cost, little environmental pollution, high safety and the like.

With the progress of technology, a nuclear reactor is widely applied to the fields of power generation, power driving and the like, so that the working environment of the nuclear reactor is changed, the reactor is arranged in a warship, a submarine or other various working environments, the reactor is influenced by gravity and other transient external forces such as inertia force in the working process, the combined influence of the gravity and the transient external forces can drive or obstruct the flow of a liquid medium in the nuclear reactor, the flow, the temperature and other thermodynamic parameters in the nuclear reactor are fluctuated, the thermodynamic and hydraulic characteristics of the nuclear reactor are influenced, and the influence of the thermodynamic and hydraulic characteristics on the operation characteristics and the safety of the nuclear reactor is unknown, so that the change of the thermodynamic and hydraulic characteristics of the nuclear reactor under the action of the transient external force is needed to be studied in order to ensure the safe and reliable operation of the nuclear reactor.

At present, a simulation test is generally performed on a nuclear reactor in a transient external force environment by combining a swing table with a nuclear reactor thermal test device, but in the simulation test, after a thermal parameter in the nuclear reactor thermal test device is detected, actual parameter change of the nuclear reactor is obtained through calculation, and the reliability of the thermal hydraulic characteristic of the nuclear reactor obtained through analysis is affected to a certain extent due to a large number of assumptions and simplified analysis in the calculation process.

Disclosure of Invention

The embodiment of the application provides a simulation system for a nuclear reactor thermal hydraulic test, which can improve the reliability of a research result of the nuclear reactor thermal hydraulic characteristic.

In one aspect, an embodiment of the present application provides a simulation system for a thermal hydraulic test of a nuclear reactor, including a test simulation subsystem and an environmental simulation subsystem, where the test simulation subsystem includes a water supply module, a flow detection module and a reactor simulation module, the reactor simulation module includes a simulation reactor and a heat exchange unit, at least part of the heat exchange unit is disposed in the simulation reactor, the water supply module is connected with the simulation reactor through the flow detection module, the water supply module is further connected with the heat exchange unit through the flow detection module, and the flow detection module is used for detecting actual flow change between the water supply module and the reactor simulation module; the environment simulation subsystem comprises a driving module and a workbench connected with the driving module, the test simulation subsystem is arranged on the workbench, and the driving module is used for driving the workbench and driving the test simulation subsystem to move in at least two degrees of freedom.

As a specific embodiment, the heat exchange unit comprises a steam subunit and a condensation subunit which are mutually communicated, the steam subunit is arranged in the simulation reactor, the steam subunit is communicated with the water supply module through the flow detection module, and the condensation subunit is communicated with the water supply module through the flow detection module.

As a specific embodiment, the reactor simulation module further comprises a pressure stabilizing unit, one end of the pressure stabilizing unit is connected with the water supply module through the flow detection module, and the other end of the pressure stabilizing unit is connected with the simulated reactor.

As a specific embodiment, the flow detection module includes a plurality of detection units, and the plurality of detection units are disposed on a plurality of flow pipes on a side of the water supply module, which is close to the reactor simulation module, in a one-to-one correspondence manner.

As a specific embodiment, the detection unit comprises a throttling structure, a first detection branch, a second detection branch and a processing subunit, wherein the throttling structure is arranged on a flow pipeline of one side of the water supply module, which is close to the reactor simulation module; the first detection branch is communicated between the upstream end and the downstream end of the throttling structure and is used for detecting the pressure difference in the throttling structure; the second detection branch is communicated between the upstream end and the downstream end of the throttling structure and is used for detecting an external force influence factor in the throttling structure; the processing subunit is respectively connected with the first detection branch and the second detection branch, and is used for calculating to obtain the actual flow change of the throttling structure according to the pressure difference and the external force influence factor in the throttling structure.

As a specific embodiment, the second detection branch comprises a first stop valve, a first detection piece and a second stop valve which are communicated in sequence, wherein the first stop valve is communicated with the upstream end of the throttling structure, the second stop valve is communicated with the downstream end of the throttling structure, and the first detection piece is connected with the processing subunit.

As a specific implementation mode, the simulation reactor comprises a reactor body, a reactor core simulator arranged in the reactor body, a power supply and at least two conductive structures, wherein the anode of the power supply, the reactor core simulator and the cathode of the power supply are sequentially connected through the two conductive structures, the reactor core simulator, the flow detection module and the water supply module are sequentially communicated, the reactor core simulator is used for generating heat energy under the action of current of the power supply, the conductive structures are used for cooling the heat energy generated by the current in the conductive process while conducting electricity, and at least part of heat exchange units are arranged in the reactor body so as to utilize the heat energy generated by the reactor core simulator.

As a specific embodiment, the conductive structure includes a first fixing member, a second fixing member, and a cooling member and a plurality of conductive members connected between the first fixing member and the second fixing member, the first fixing member is connected with a positive electrode or a negative electrode of the power supply, the second fixing member is connected with the core simulator, and the cooling member is used for cooling the conductive members during the conductive process.

As a specific embodiment, the conductive structure further includes an insulating member surrounding the periphery of each conductive member, and the insulating member is provided with a plurality of openings exposing at least a portion of the conductive members to enhance the cooling effect.

As a specific embodiment, the cooling member comprises a cooling machine and a cooling pipeline which are mutually communicated, the cooling pipeline is connected between the first fixing member and the second fixing member, a plurality of flow holes are formed in the cooling pipeline, the cooling machine is used for inputting cooling air into the cooling pipeline, and the flow holes are used for enabling the cooling air in the cooling pipeline to flow to the opening of each conductive member.

As a specific embodiment, the plurality of cooling pipes are arranged at intervals with the plurality of conductive members.

As a specific embodiment, the core simulator comprises a cartridge, a first conductive element and a second conductive element, wherein the positive electrode of the power supply, the conductive structure, the first conductive element and the input end of the cartridge are sequentially connected, the negative electrode of the power supply, the conductive structure, the second conductive element and the output end of the cartridge are sequentially connected, the first conductive element and the second conductive element are also communicated with the water supply module through the flow detection module, and the cartridge is used for generating heat energy under the action of current.

As a specific embodiment, the cartridge includes a first conductive member, a second conductive member, and a separation member and at least two heat generating members disposed between the first conductive member and the second conductive member, the separation member being disposed between the two heat generating members and penetrating the second conductive member to separate the second conductive member into an input end and an output end insulated from each other, the input end of the second conductive member being connected to the first conductive element, and the output end of the second conductive member being connected to the second conductive element.

As a specific embodiment, the driving module comprises a motion data generating unit, a state control unit and an action control unit which are sequentially connected, wherein the motion data generating unit is used for generating motion data and sending the motion data to the state control unit, the state control unit is used for generating a workbench motion signal and sending the workbench motion signal to the action control unit, and the action control unit is used for driving the workbench to move according to the workbench motion signal.

According to the simulation system for the thermal hydraulic test of the nuclear reactor, the thermal hydraulic test device of the nuclear reactor is simulated through the reactor simulation module and the water supply module in the test simulation subsystem, and the test simulation subsystem is arranged on the workbench in the environment simulation subsystem, when the driving module drives the workbench to move, the workbench drives the reactor simulation subsystem to move, so that the state of the thermal hydraulic test device of the nuclear reactor when various degrees of freedom are generated under the action of transient external force is simulated, in the process, the actual flow change between the reactor simulation module and the water supply module in the movement process is directly detected through the flow detection module, so that the actual flow change can be obtained without calculation, the influence of various error factors in the calculation process on the research result of the thermal hydraulic characteristic of the nuclear reactor is eliminated, and the reliability of the research result is improved.

Drawings

In order to more clearly illustrate the technical solutions of the embodiments of the present application, the drawings that are needed in the embodiments of the present application will be briefly described, and it is possible for a person skilled in the art to obtain other drawings according to these drawings without inventive effort.

FIG. 1 is a schematic diagram of a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application;

FIG. 2 is a schematic structural view of a reactor simulation module of a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application;

FIG. 3 is a schematic diagram of a heat exchange unit in a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application;

FIG. 4 is a schematic diagram of a voltage stabilizing unit in a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application;

FIG. 5 is a schematic structural view of a feedwater module in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application;

FIG. 6 is a schematic structural view of a detection unit in a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application;

FIG. 7 is a schematic structural view of an electrically conductive structure in a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application;

FIG. 8 is a schematic structural view of an electrically conductive member in a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application;

FIG. 9 is a schematic view of a portion of a cooling element in a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application;

FIG. 10 is a schematic structural view of a core simulator in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application;

FIG. 11 is a schematic structural view of a drive module in a simulation system for a thermal hydraulic test of a nuclear reactor provided in some embodiments of the present application.

Reference numerals illustrate:

100. a water supply module; 110. A water supply unit; 120. A trace water supplementing unit;

111. a water storage structure; 112. A water feed pump; 113. A heating element;

121. a water supplementing pump; 200. A flow detection module; 211. A throttle structure;

212. a first detection branch; 2121. A second detecting member; 213. A second detection branch;

2131. a first stop valve; 2132. A first detecting member; 2133. A second shut-off valve;

214. A processing subunit; 300. A reactor simulation module; 310. Simulating a reactor;

311. a reactor body; 312. A core simulator; 3121. A cartridge;

3121a, a first conductive member; 3121b, a second conductive member; 3121c, an isolation member;

3121d, heat generating components; 3122. A first conductive element; 3123. A second conductive element;

313. a power supply; 314. The conductive structure 3141, the first mount;

3142. a second fixing member; 3143. A cooling member; 3143a, a chiller;

3143b, cooling tubing; 3143c, flow holes; 3144. A conductive member;

3145. an insulating member; 3146. An opening; 320. A heat exchange unit;

321 steam subunit; 322. A condensing subunit; 3221. A condenser;

3222. a circulating water pump; 3223. A water storage structure; 330. A voltage stabilizing unit;

331. a voltage stabilizer; 332. An inflator pump; 333. A pressure regulating valve;

400. a driving module; 410. A motion data generation unit; 420. a state control unit;

430. an action control unit; 431. A control subunit; 432. drive subunit

500. A work table; 510. A table body; 520. An actuation structure;

600. and a parameter control module.

Detailed Description

Features and exemplary embodiments of various aspects of the present application are described in detail below to make the objects, technical solutions and advantages of the present application more apparent, and to further describe the present application in conjunction with the accompanying drawings and the detailed embodiments. It should be understood that the specific embodiments described herein are merely configured to explain the present application and are not configured to limit the present application. It will be apparent to one skilled in the art that the present application may be practiced without some of these specific details. The following description of the embodiments is merely intended to provide a better understanding of the present application by showing examples of the present application.

It is noted that relational terms such as first and second, and the like are used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Moreover, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising … …" does not exclude the presence of other like elements in a process, method, article or apparatus that comprises the element.

In order to solve the problems in the prior art, the embodiment of the application provides a simulation system for a thermal hydraulic test of a nuclear reactor.

Fig. 1 is a schematic structural view of a simulation system for a thermal hydraulic test of a nuclear reactor according to some embodiments of the present application, and fig. 2 is a schematic structural view of a reactor simulation module of a simulation system for a thermal hydraulic test of a nuclear reactor according to some embodiments of the present application.

As shown in fig. 1 and 2, an embodiment of the present application provides a simulation system for a thermal hydraulic test of a nuclear reactor, including a test simulation subsystem (not shown) and an environment simulation subsystem (not shown), the test simulation subsystem including a water supply module 100, a flow detection module 200 and a reactor simulation module 300, the reactor simulation module 300 including a simulation reactor 310 and a heat exchange unit 320, at least part of the heat exchange unit 320 being disposed inside the simulation reactor 310, the water supply module 100 being connected to the simulation reactor 310 through the flow detection module 200, the water supply module 100 being further connected to the heat exchange unit 320 through the flow detection module 200, the flow detection module 200 being configured to detect an actual flow change between the water supply module 100 and the reactor simulation module 300; the environment simulation subsystem comprises a driving module 400 and a workbench 500 connected with the driving module 400, the test simulation subsystem is installed on the workbench 500, and the driving module 400 is used for driving the workbench 500 and driving the test simulation subsystem to move in at least two degrees of freedom.

It can be understood that the actual flow change in the embodiment of the present application refers to the actual flow change of the test simulation subsystem after the external force influence caused by the motion is removed. In the process that the workbench 500 drives the test simulation subsystem to move, due to the driving or blocking effect of external forces such as inertia force brought by movement on the liquid flow in the test simulation subsystem, in order to ensure the accuracy of analysis on the thermal hydraulic characteristics of the test simulation subsystem and further ensure the reliability of research on the operation characteristics and safety of the test simulation subsystem under the influence of transient external force, the flow detection module 200 is arranged in the test simulation subsystem, so that the influence of the transient external force on the driving or blocking effect of the liquid in the test simulation subsystem can be eliminated, the actual flow change in the test simulation subsystem can be directly obtained without improving the calculation, various error factors in the calculation process are eliminated, and the accuracy of research results is improved.

According to the simulation system for the thermal hydraulic test of the nuclear reactor, the thermal hydraulic test device of the nuclear reactor is simulated through the reactor simulation module 300 and the water supply module 100 in the test simulation subsystem, and the test simulation subsystem is arranged on the workbench 500 in the environment simulation subsystem, when the workbench 500 is driven by the driving module 400 to move, the workbench 500 drives the reactor simulation subsystem to move, so that states of the thermal hydraulic test device of the nuclear reactor when various degrees of freedom move under the action of transient external force are simulated, in the process, the actual flow change between the reactor simulation module 300 and the water supply module 100 in the movement process is directly detected through the flow detection module 200, so that the actual flow change can be obtained without calculation, the influence of various error factors in the calculation process on the research result of the thermal hydraulic characteristics of the test simulation subsystem is eliminated, and the reliability of the research result is improved.

In addition, since the simulated reactor 310 generates huge heat energy during operation, in order to prevent safety accidents caused by overheating of the simulated reactor 310, at least a portion of the heat exchange unit 320 is disposed inside the simulated reactor 310, water is supplied into the heat exchange unit 320 through the water supply module 100, heat energy conversion is achieved through evaporation and condensation of water, heat energy in the simulated reactor 310 is transferred to the outside of the simulated reactor 310, and safety accidents caused by overheating of the simulated reactor 310 are prevented; in addition, since the heat released by the simulated reactor 310 is relatively large, a relatively large current is often required inside the simulated reactor 310 to cause the simulated reactor 310 to release heat, and when the current is relatively large, heat energy is inevitably generated on the current path, so that the resistivity of the current path is affected and even the current path is shorted, and therefore, by sequentially connecting the simulated reactor 310, the flow detection module 200 and the water supply module 100, liquid water is filled into the simulated reactor 310 through the water supply module 100, the current path in the simulated reactor 310 is cooled, and the constant resistivity of the current path is ensured to a certain extent and even the current path is not shorted due to overheating; in addition, in the process of supplying water to the simulation reactor 310 and the heat exchange unit 320 through the water supply module 100, since the test simulation subsystem is installed on the table 500 of the environment simulation subsystem and the table 500 is in a moving state, the flow detection module 200 is provided between the water supply module 100 and the simulation reactor 310 and between the water supply unit 110 and the heat exchange unit 320, so that the actual flow variation between the water supply module 100 and the simulation reactor 310 and between the water supply unit 110 and the heat exchange unit 320 can be directly detected through the flow detection module 200 without calculation, and the thermal hydraulic characteristics of the test simulation subsystem are researched and analyzed, thereby ensuring the reliability of the research result of the thermal hydraulic characteristics of the test simulation subsystem.

In this embodiment of the present application, the above modules and the devices may be all connected by flexible connection, so that when the reactor simulation subsystem moves under the driving of the workbench 500, the connection between the components will not break due to the movement.

It will be appreciated that the degree of time synchronisation between elements in a nuclear reactor is affected by transient external forces, for example in a nuclear reactor where the external water supply has been shut down but the internal reactor core is still in operation, the operational safety of the reactor may be affected by the stalling of certain components in the reactor, and therefore the impact of transient external forces on the lifting load mobility of the nuclear reactor may be studied by the reactor simulation subsystem simulating a nuclear reactor thermodynamic hydraulic test device under the influence of transient external forces to solve the above problems.

Referring to fig. 1, as a specific embodiment, the workbench 500 includes a table body 510 and an actuating structure 520 connected to the table body 510, where the actuating structure 520 is connected to the driving module 400 and drives the table body 510 to move under the control of the driving module 400. Specifically, under the driving of the driving module 400, the actuating structure 520 may drive the table body 510 to move along multiple degrees of freedom, and the actuating structure 520 may be various types of actuators, for example: the actuating structure 520 may be other connecting structures that are connected between the table body 510 and the driving module 400 and drive the table body 510 to move under the driving of the driving module 400, such as a fluid actuator, a gas actuator, a piezoelectric ceramic actuator, or a piezoelectric thin film actuator.

As a specific embodiment, the actuating structure 520 may be a plurality of actuating structures 520 connected between the driving module 400 and the table body 510, so that the table body 510 can move along more degrees of freedom, thereby simulating the state of the nuclear reactor thermohydraulic test device when moving under the action of transient external force to the greatest extent.

For example, the number of the actuating structures 520 may be six, so that the table body 510 may move along at least six degrees of freedom under the driving of the six actuating structures 520.

Fig. 3 illustrates a schematic structural diagram of a heat exchange unit in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application.

As shown in fig. 3, as a specific embodiment, the heat exchange unit 320 includes a steam subunit 321 and a condensation subunit 322 that are mutually communicated, the steam subunit 321 is disposed inside the simulated reactor 310, the steam subunit 321 is communicated with the feedwater module 100 through the flow detection module 200, and the condensation subunit 322 is communicated with the feedwater module 100 through the flow detection module 200.

Specifically, in order to realize the transfer of the heat energy generated by the simulated reactor 310, the heat exchange unit 320 includes a steam subunit 321 and a condensation subunit 322, wherein the steam subunit 321 is disposed inside the simulated reactor 310, when the simulated reactor 310 releases heat, the liquid water in the steam subunit 321 absorbs heat and evaporates, the evaporated water vapor flows to the condensation subunit 322 to perform condensation heat release, thereby converting the heat energy in the simulated reactor 310 to the outside of the simulated reactor 310, and meanwhile, the water vapor in the condensation subunit 322 releases heat and solidifies into liquid water and flows into the water supply module 100 through the circulation pipeline, thereby realizing the recycling of the liquid water.

As a specific embodiment, the steam subunit 321 includes a steam generator simulator disposed inside the simulated reactor 310, one end of the steam generator simulator is in communication with the feedwater module 100 through the flow detection module 200, and the other end of the steam generator simulator is in communication with the condensing subunit 322.

The steam generator simulation piece can be a straight-flow type steam generator simulation piece, a vertical steam generator simulation piece, a natural circulation steam generator simulation piece and a U-shaped tubular steam generator simulation piece.

With continued reference to fig. 3, as a specific embodiment, the condensation subunit 322 may include a condenser 3221, a circulating water pump 3222 and a water storage structure 3223, the condenser 3221 includes a high temperature region and a low temperature region, the high temperature region of the condenser 3221 is respectively communicated with the steam subunit 321 and the water supply module 100, and the low temperature region of the condenser 3221 is communicated with the water storage structure 3223 through the circulating water pump 3222.

The water storage structure 3223 may be a water tower, or may be another structure capable of storing liquid, for example, a water tank, or the like.

In the present embodiment, after the high-temperature steam in the steam subunit 321 enters the high-temperature region of the condenser 3221, due to the cooling effect of the low-temperature region of the condenser 3221, the heat energy in the high-temperature steam is transferred to be converted into liquid water, and flows into the water supply module 100, the low-temperature region of the condenser 3221 is communicated with the water storage structure 3223 through the circulating water pump 3222, so that the liquid water in the low-temperature region of the condenser 3221 and the liquid water in the water storage structure 3223 are continuously circulated through the circulating water pump 3222, so as to ensure that the temperature of the cooling water in the low-temperature region of the condenser 3221 is at a lower temperature.

Referring to fig. 2, as a specific embodiment, the reactor simulation module 300 further includes a pressure stabilizing unit 330, one end of the pressure stabilizing unit 330 is connected to the water supply module 100 through the flow detection module 200, and the other end of the pressure stabilizing unit 330 is connected to the simulated reactor 310.

In the process of starting up the simulated reactor 310 and closing the simulated reactor 310, the internal pressure of the simulated reactor 310 is unstable due to the huge temperature change in the simulated reactor 310, so that in order to ensure that the internal pressure of the simulated reactor 310 is in a safe and stable state, the pressure stabilizing unit 330 connected with the simulated reactor 310 is arranged, and in order to ensure that the gas-liquid state in the pressure stabilizing unit 330 is stable, the pressure stabilizing unit 330 is also arranged to be connected with the water supply module 100, thereby ensuring that the simulated reactor 310 is in a stable pressure environment and ensuring the operation safety of the simulated reactor 310.

Fig. 4 is a schematic structural diagram of a voltage stabilizing unit in a simulation system for a thermal hydraulic test of a nuclear reactor according to some embodiments of the present application.

As shown in fig. 4, as a specific embodiment, the pressure stabilizing unit 330 includes a pressure stabilizer 331, an inflator 332, and a pressure regulating valve 333 disposed on the pressure stabilizer 331, one end of the pressure stabilizer 331 is connected to the water supply module 100 through the flow detection module 200, the other end of the pressure stabilizer 331 is connected to the analog reactor 310, and the inflator 332 is connected to the pressure stabilizer 331.

In the present embodiment, when the pressure in the simulated reactor 310 is too low, the pressure stabilizer 331 is filled with gas through the inflator 332, and the pressure stabilizer 331 is filled with liquid through the water supply module 100, so that the pressure in the simulated reactor 310 is increased and the pressure stabilizer 331 is in a gas-liquid saturated equilibrium state; when the pressure in the simulated reactor 310 is too high, the pressure in the simulated reactor 310 is reduced to a certain extent by opening the pressure regulating valve 333 to allow the gas and liquid portions located in the pressure regulator 331 to be discharged, so that the regulation of the pressure in the simulated reactor 310 is realized; in addition, since the flow detection module 200 is disposed between the voltage stabilizer 331 and the water supply module 100, when the workbench 500 in the environment simulation subsystem drives the test simulation subsystem to be in a motion state, i.e. in an external force action state, the flow detection module 200 can directly detect the actual flow change between the water supply module 100 and the voltage stabilizing unit 330 without calculation, thereby realizing research and analysis on the thermodynamic characteristics of the simulated reactor 310 and ensuring the reliability of the research result.

As a specific embodiment, the pressure stabilizing unit 330 may further include a gas storage structure, for example, a gas storage tank, a gas storage bottle, and the like, where the gas storage structure is connected to the inflator 332, so that when the pressure in the simulated reactor 310 is too low, the inflator 332 charges the gas in the gas storage structure into the pressure stabilizer 331, thereby realizing the adjustment of the pressure in the simulated reactor 310, and the gas storage structure may further store the released gas when the pressure in the simulated reactor 310 is too high and the pressure needs to be released, thereby avoiding the waste of resources.

FIG. 5 illustrates a schematic block diagram of a feedwater module in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application.

As shown in fig. 5, as a specific embodiment, the water supply module 100 includes a water supply unit 110 and a micro water supply unit 120, the water supply unit 110 is in one-to-one correspondence with the simulation reactor 310, the steam subunit 321 and the condensation subunit 322 through the flow detection module 200, one end of the micro water supply unit 120 is in communication with the pressure stabilizing unit 330 through the flow detection module 200, and the other end of the micro water supply unit 120 is in communication with the water supply unit 110.

Since the amount of liquid water required in the simulation reactor 310, the steam subunit 321 and the condensation subunit 322 is large, and the pressure in the reactor simulation module 300 is only required to be regulated in the pressure stabilizing unit 330 by injecting liquid water and gas into the pressure stabilizing unit 330 when the pressure in the reactor simulation module 300 is small, in this process, only a small amount of liquid water is required to be injected, so that in order to accurately regulate the amount of liquid water injected into the pressure stabilizing unit 330, the pressure regulating effect of the pressure stabilizing unit 330 is ensured, liquid water is injected into the simulation reactor 310, the steam subunit 321 and the condensation subunit 322 through the water supply unit 110, and liquid water is injected into the pressure stabilizing unit 330 through the micro water supplementing unit 120, so that the accurate regulation of the pressure in the reactor simulation module 300 is realized, the simulation of the reactor simulation module 300 is ensured to the greatest extent, and the reliability of the study of hydraulic characteristics under the influence of transient external force by the simulation system is improved.

As a specific embodiment, micro-makeup unit 120 may also be in communication with simulated reactor 310, steam subunit 321, and condensate subunit 322 to replenish liquid water to simulated reactor 310, steam subunit 321, and condensate subunit 322.

Referring to fig. 5, as a specific embodiment, the water supply unit 110 includes a water storage structure 111, a water supply pump 112, and a heating element 113, wherein a water outlet of the water storage structure 111 is respectively connected to the water supply pump 112 and the micro water replenishing unit 120, the heating element 113 is disposed on a side of the water supply pump 112 away from the water storage structure 111, and a side of the heating element 113 away from the water supply pump 112 is correspondingly connected to the simulation reactor 310, the steam subunit 321, and the condensation subunit 322 through the flow detection module 200, and the heating element 113 is used for adjusting a temperature of liquid water flowing out of the water storage structure 111.

The water storage structure 111 may be any device capable of storing liquid, such as a deoxidizing water tank, etc., and the heating element 113 may be various devices capable of heating liquid, such as an electric heating element 113 or a chemical heating element 113, etc.

In this embodiment, the water outlet of the water storage structure 111 is respectively connected to the water feeding pump 112 and the micro water supplementing unit 120, so that when water is supplied to the micro water supplementing unit 120, liquid water is pumped into the simulation reactor 310, the steam subunit 321 and the condensation subunit 322 through the water feeding pump 112, and because the simulation reactor 310, the steam subunit 321 and the condensation subunit 322 generally have certain requirements on the temperature of the liquid water, the heating element 113 is arranged on one side of the water feeding pump 112 far away from the water storage structure 111, so that the temperature of the liquid water flowing out of the water storage structure 111 is regulated, the simulation of the nuclear reactor is realized to the greatest extent by the reactor simulation module 300, and the reliability of the study of the thermodynamic characteristics of the nuclear reactor under the influence of transient external force by the simulation system is improved.

Referring to fig. 5, as a specific embodiment, the micro water replenishing unit 120 may include a water replenishing pump 121, one end of the water replenishing pump 121 is connected to the water supplying unit 110, and the other end of the water replenishing pump 121 is connected to the pressure stabilizing unit 330 through the flow detecting module 200. Of course, the make-up pump 121 may also simulate a one-to-one communication of the reactor 310, steam subunit 321, and condensate subunit 322.

Referring to fig. 1, as a specific embodiment, the flow detection module 200 includes a plurality of detection units (not shown) disposed on a plurality of flow pipes on a side of the feedwater module 100 near the reactor simulation module 300 in a one-to-one correspondence.

It will be appreciated that the devices in the test simulation subsystem are all communicated through a flow pipeline, so that the plurality of detection units in the flow detection module 200 may be disposed on the plurality of flow pipelines between the feedwater module 100 and the reactor simulation module 300 in a one-to-one correspondence manner, specifically, the detection units may be disposed on the flow pipeline between the feedwater module 100 and the simulation reactor 310, the flow pipeline between the feedwater module 100 and the steam subunit 321, the flow pipeline between the feedwater module 100 and the condensation subunit 322, and the flow pipeline between the feedwater module 100 and the pressure stabilizing unit 330.

In this embodiment, the detection units are disposed on the plurality of flow pipes on the side of the water supply module 100, which is close to the reactor simulation module 300, in a one-to-one correspondence manner, so that the actual flow change of each flow pipe between the water supply module 100 and the reactor simulation module 300 is detected individually, thereby further ensuring the accuracy of the detection result of the actual flow change in the reactor simulation subsystem and improving the reliability of the research result of the thermal hydraulic characteristics of the test simulation subsystem.

FIG. 6 is a schematic diagram of a detection unit in a simulation system for a thermal hydraulic test of a nuclear reactor according to some embodiments of the present application

As shown in fig. 6, as a specific embodiment, the detection unit includes a throttling structure 211, a first detection branch 212, a second detection branch 213, and a processing subunit 214, where the throttling structure 211 is disposed on a flow channel on a side of the feedwater module 100 near the reactor simulation module 300; the first detection branch 212 is communicated between the upstream end and the downstream end of the throttling structure 211, and the first detection branch 212 is used for detecting the pressure difference in the throttling structure 211; the second detection branch 213 is connected between the upstream end and the downstream end of the throttling structure 211, and the second detection branch 213 is used for detecting an external force influence factor in the throttling structure 211; the processing subunit 214 is connected to the first detecting branch 212 and the second detecting branch 213, and the processing subunit 214 is configured to calculate an actual flow change of the throttling structure 211 according to the pressure difference and the external force influence factor in the throttling structure 211.

The throttle structure 211 may be a venturi throttle, or may be other throttle of various types, for example, the throttle structure 211 may also be an orifice type throttle, a nozzle type throttle, or the like. In the detection unit, the throttle structure 211, the first detection branch 212, and the second detection branch 213 may communicate through a pulse tube, and of course, may also communicate through the above-described flow channel.

It will be appreciated that the upstream end of the throttling structure 211 is connected to a side of the flow conduit adjacent to the feedwater module 100, the downstream end of the throttling structure 211 is connected to a side of the flow conduit adjacent to the reactor simulation module 300, and a local constriction is formed between the upstream end and the downstream end of the throttling structure 211, and when the liquid in the feedwater module 100 flows to the downstream end of the throttling structure 211 through the upstream end of the throttling structure 211, the flow velocity of the liquid increases and the static pressure decreases as the liquid flows to the local constriction, so that a certain static pressure difference, that is, a differential pressure, is generated between the upstream end and the downstream end of the throttling structure 211.

It can be understood that the external force influence factor is the influence of the external force applied to the corresponding throttle structure 211 during the movement on the pressure difference.

In this embodiment, by installing the throttling structure 211 on the flow conduit on the side of the water supply module 100 close to the reactor simulation module 300, a certain pressure difference is generated between the upstream end and the downstream end of the throttling structure 211, and by communicating the first detecting branch 212 between the upstream end and the downstream end of the throttling structure 211 and communicating the second detecting branch 213 between the upstream end and the downstream end of the throttling structure 211, that is, by communicating the first detecting branch 212 and the second detecting branch 213 in parallel between the upstream end and the downstream end of the throttling structure 211, the pressure difference in the throttling structure 211 is detected by the first detecting branch 212, the external force influence factor in the throttling structure 211 is detected by the second detecting branch 213, and by subtracting the external force influence factor detected by the processing subunit 214, the actual pressure difference after the external force influence is removed in the throttling structure 211 is obtained, and by the actual pressure difference, the actual flow rate change in the throttling structure 211 is obtained, that is, the actual flow rate change is the corresponding to the actual flow rate change of the throttling structure is simulated by the thermal flow rate of the thermal flow of the reactor simulation module, and the thermal flow of the thermal reactor is simulated by the integrated test system, and the thermal flow characteristics of the thermal reactor are improved.

With continued reference to fig. 6, as a specific embodiment, the second detection branch 213 includes a first stop valve 2131, a first detection element 2132, and a second stop valve 2133 that are sequentially connected, where the first stop valve 2131 is connected to an upstream end of the throttling structure 211, the second stop valve 2133 is connected to a downstream end of the throttling structure 211, and the first detection element 2132 is connected to the processing subunit 214.

First, before the table 500 does not drive the test simulation subsystem to move, the first stop valve 2131 and the second stop valve 2133 are opened to fill the second detection branch 213 with liquid water, and then the first stop valve 2131 and the second stop valve 2133 are closed, so that during the process of the table 500 driving the test simulation subsystem to move, the liquid water in the second detection branch 213 is in a relatively static state, at this time, the first detection part 2132 in the second detection branch 213 is only acted by an external force and not acted by a liquid pressure difference in the throttling structure 211, so that the first detection part 2132 can detect the influence of the external force acted by the corresponding throttling structure 211 on the pressure difference in the throttling structure 211, that is, the first detecting piece 2132 detects the external force influence factor of the corresponding throttling structure 211, so that the processing subunit 214 performs subtraction operation on the differential pressure detected by the first detecting branch 212 and the external force influence factor detected by the second detecting branch 213 to obtain an actual differential pressure in the throttling structure 211 after the external force influence is removed, and then the actual differential pressure is used for obtaining an actual flow change in the throttling structure 211, wherein the actual flow change of the throttling structure 211 is the actual flow change of the corresponding flow pipeline, so that the reliability of the research structure on the thermal hydraulic characteristics of the test simulation subsystem is improved by comprehensively analyzing the thermal hydraulic characteristics of other flow pipelines between the integrated water supply module 100 and the reactor simulation module 300.

With continued reference to fig. 6, in order to detect the pressure difference between the upstream end and the downstream end of the throttling structure 211, as a specific embodiment, the first detecting branch 212 includes a second detecting element 2121, where the second detecting element 2121 is disposed between the upstream end and the downstream end of the throttling structure 211, and the second detecting element 2121 is configured to detect the pressure difference between the upstream end and the downstream end of the throttling structure 211.

It is understood that the first detector 2132 and the second detector 2121 can each be differential pressure sensors. In this embodiment, no stop valve is disposed on two sides of the second detecting element 2121, so that the second detecting element 2121 can directly detect the differential pressure in the throttling structure 211, the first stop valve 2131 and the second stop valve 2133 are disposed on two sides of the first detecting element 2132, the first stop valve 2131 and the second stop valve 2133 are closed after the second detecting branch 213 is filled with liquid water, the first detecting element 2132 can detect the influence of the external force received by the corresponding throttling structure 211 on the differential pressure in the throttling structure 211, that is, the first detecting element 2132 detects the external force influence factor of the corresponding throttling structure 211, so that the processing subunit 214 performs subtraction operation on the differential pressure detected by the first detecting branch 212 and the external force influence factor detected by the second detecting branch 213 to obtain the actual differential pressure after the external force influence is removed from the throttling structure 211, and then the actual flow rate change in the throttling structure 211 is obtained through the actual differential pressure.

As a specific embodiment, in the same detection unit, the horizontal distance between the first detection piece 2132 and the second detection piece 2121 is as small as possible, and the setting heights between the first detection piece 2132 and the second detection piece 2121 are as consistent as possible, so that the influence of the geometrical space position difference on the detection results of the first detection piece 2132 and the second detection piece 2121 is eliminated to the greatest extent in the process of driving the test simulation subsystem to move by the workbench 500, thereby improving the accuracy of detecting the actual flow change of the corresponding flow pipeline and further improving the reliability of analysis and research on the thermal hydraulic characteristics of the test simulation subsystem.

It will be appreciated that, in order to eliminate the influence of the geometrical spatial position difference on the detection results of the first detecting element 2132 and the second detecting element 2121 as much as possible, each flow conduit in the first detecting branch 212 and the corresponding flow conduit in the second detecting branch 213 may be connected together by binding or the like, so as to reduce the geometrical spatial difference between the first detecting branch 212 and the second detecting branch 213 and improve the accuracy of detecting the actual flow change.

Referring to fig. 2 again, as a specific embodiment, the simulated reactor 310 includes a reactor body 311, a core simulator 312 disposed inside the reactor body 311, a power supply 313, and at least two conductive structures 314, wherein an anode of the power supply 313, the core simulator 312, and a cathode of the power supply 313 are sequentially connected through the two conductive structures 314, the core simulator 312 is configured to generate heat energy under the effect of the current of the power supply 313, the conductive structures 314 are configured to cool the heat generated by the current in the conductive process while conducting electricity, and at least a portion of the heat exchange unit 320 is disposed inside the reactor body 311 to utilize the heat energy generated by the core simulator 312.

In the simulation reactor 310, two conductive structures 314 may be connected between the positive electrode of the power supply 313 and the input end of the core simulator 312 and between the negative electrode of the power supply 313 and the output end of the core simulator 312, respectively, although there may be a plurality of conductive structures 314, for example, three conductive structures 314, two conductive structures 314 may be sequentially connected between the positive electrode of the power supply 313 and the input end of the core simulator 312, and only one conductive structure 314 may be connected between the negative electrode of the power supply 313 and the output end of the core simulator 312, or only one conductive structure 314 may be connected between the positive electrode of the power supply 313 and the input end of the core simulator 312, and two conductive structures 314 may be sequentially connected between the negative electrode of the power supply 313 and the output end of the core simulator 312.

In order to ensure that the simulation reactor 310 performs simulation of the nuclear reactor to the maximum extent, thereby improving reliability of research on thermal hydraulic characteristics of the nuclear reactor under the influence of transient external force through the simulation system, it is necessary that the simulation reactor 310 can generate a large amount of heat energy during operation as in a real nuclear reactor, and therefore, it is necessary to set a current flowing into the simulation reactor 310 to be large enough, and it is understood that a large current generates a large amount of heat during conduction, and thus, when the current flows in a loop between the power supply 313 and the simulation reactor 310, a wire is easy to cause an overheat short circuit due to the large heat, and therefore, in order to avoid the overheat short circuit of the conductive structure 314 due to the excessive current during conduction, the application adopts the conductive structure 314 to cool the heat generated by the current during conduction, thereby ensuring that the conductive structure 314 does not cause the overheat short circuit due to the excessive current.

In the present embodiment, by disposing the core simulator 312 inside the reactor body 311, the anode of the power supply 313, the core simulator 312, and the cathode of the power supply 313 are respectively connected through at least two conductive structures 314, so that a current loop is formed between the power supply 313 and the core simulator 312, and the core simulator 312 generates heat under the action of the current, thereby realizing the simulation of the nuclear reactor; and, when the current flows in the loop between the power supply 313 and the simulation reactor 310, the current is conducted through the conductive structure 314, and the conductive structure 314 can cool the heat generated by the current in the conductive process while conducting the current, so that the overheat short circuit of the conductive structure 314 caused by overlarge current in the working process of the simulation reactor 310 is avoided, the maximum simulation of the simulation reactor 310 on the nuclear reactor is ensured, the reliability of the research on the thermodynamic hydraulic characteristics of the nuclear reactor under the influence of transient external force by the simulation system is improved, and meanwhile, the fact that the simulation reactor 310 is not overheated short circuit caused by huge heat generated in the current loop is ensured, so that the operation safety and the service life of the simulation reactor 310 are improved to a certain extent.

To ensure that the simulated reactor 310 performs a simulation of the nuclear reactor to a maximum extent, thereby improving reliability of the study of the thermodynamic and hydraulic characteristics of the nuclear reactor under the influence of transient external forces by the simulation system, as a specific embodiment, the reactor body 311 may include a pressure shell, an in-reactor component simulator, an chlorophytum simulator, etc., it being understood that the reactor body 311 may also include any other nuclear reactor element of the simulated reactor 310 other than the core simulator 312.

It will be appreciated that the core simulator 312 may include fuel assemblies for releasing heat upon power-up, although the core simulator 312 may include other elements for simulating a nuclear reactor core, for example, the core simulator 312 may include control rod simulators to simulate the structure of a nuclear reactor to the greatest extent, reducing the gap between the simulated reactor 310 and a real nuclear reactor, and thus improving reliability of the results of the study.

Fig. 7 illustrates a schematic structural diagram of an electrically conductive structure in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application.

As shown in fig. 7, as a specific embodiment, the conductive structure 314 includes a first fixing member 3141, a second fixing member 3142, and a cooling member 3143 and a plurality of conductive members 3144 connected between the first fixing member 3141 and the second fixing member 3142, the first fixing member 3141 being connected to the positive or negative electrode of the power supply 313, the second fixing member 3142 being connected to the core simulator 312, the cooling member 3143 being used to cool the conductive members 3144 during the conduction.

Specifically, the conductive member 3144 may be a metal conductive member 3144 such as a copper rod, a copper braid, or aluminum, or may be a conductive member 3144 having a conductive function, for example, a polymer conductive material, conductive rubber, conductive plastic, or the like.

It will be appreciated that the first and

second fixtures

3141 and 3142 are also made of conductive materials that conduct current in order to allow a current loop to be formed between the power supply 313 and the core simulator 312.

In the present embodiment, the first fixing member 3141 is connected to the positive electrode or the negative electrode of the power supply 313, and the second fixing member 3142 is connected to the core simulator 312, so that in the process of supplying power to the core simulator 312 from the power supply 313, the current is conducted through the conductive member 3144, and in the process of conducting, the conductive member 3144 is cooled through the cooling member 3143, so that excessive heat generated by the conductive member 3144 due to excessive current in the process of conducting is avoided, and the operation safety and the service life of the simulation reactor 310 are improved to a certain extent.

Fig. 8 illustrates a schematic structural diagram of an electrically conductive member in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application.

As shown in fig. 8, in order to prevent the plurality of conductive members 3144 from affecting the stability of the current in the conductive process due to the mutual contact, as a specific embodiment, the conductive structure 314 further includes an insulating member 3145 provided around the outer circumference of each conductive member 3144, a plurality of openings 3146 are opened in the insulating member 3145, and the openings 3146 expose at least part of the conductive members 3144 to enhance the cooling effect.

The insulator 3145 may be made of an organic material or an inorganic material, and for example, the insulator 3145 may be an insulating paint, an insulating paste, or a rubber coating the conductor 3144, and the insulator 3145 may be made of an inorganic material such as ceramic or mica.

In the present embodiment, the insulating member 3145 is provided at the outer periphery of each of the conductive members 3144 so as to avoid mutual contact between the plurality of conductive members 3144 and to improve stability in the current conduction process, but since the cooling effect of the cooling member 3143 on the conductive members 3144 is reduced to some extent after the insulating member 3145 wraps the conductive members 3144, in order to ensure that the cooling member 3143 can effectively cool the heat generated by the conductive members 3144, a plurality of openings 3146 are opened in the insulating member 3145 and the conductive members 3144 are exposed through the plurality of openings 3146, thereby ensuring the conductive effect of the cooling member 3143 on the conductive members 3144 while insulating the plurality of conductive members 3144 from each other.

FIG. 9 illustrates a partial schematic of a cooling element in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application.

As shown in fig. 7 and 9, as a specific embodiment, the cooling member 3143 includes a cooling machine 3143a and a cooling duct 3143b which are communicated with each other, the cooling duct 3143b is connected between the first fixing member 3141 and the second fixing member 3142, a plurality of circulation holes 3143c are opened in the cooling duct 3143b, the cooling machine 3143a is used for inputting cooling gas into the cooling duct 3143b, and the circulation holes 3143c are used for supplying the cooling gas in the cooling duct 3143b to the opening 3146 of each conductive member 3144.

The cooler 3143a may be a blower, an air cooler 3143a, a nitrogen cooler 3143a, or the like, or may be another type of gaseous cooler 3143a.

In the present embodiment, by communicating the cooler 3143a with the cooling duct 3143b and disposing the cooling duct 3143b between the first fixing member 3141 and the second fixing member 3142, and by providing the plurality of flow holes 3143c in the cooling duct 3143b, after the cooling air is introduced into the cooling duct 3143b through the cooler 3143a, the cooling air flows along the flow duct to the surrounding conductive member 3144, thereby achieving cooling of the surrounding conductive member 3144, and since the plurality of openings 3146 are provided in the insulating member 3145 around the circumference of the conductive member 3144, the cooling air can directly contact with the conductive member 3144 after flowing to the conductive member 3144, thereby further improving the cooling effect on the conductive member 3144, and effectively preventing the overheating short circuit phenomenon of the conductive member 3144 due to excessive current in the conductive process.

As a specific embodiment, the plurality of flow holes 3143c may be disposed at equal intervals, so that the cooling gas in the cooling duct 3143b may uniformly flow at each of the conductive members 3144, thereby achieving uniform cooling of each of the conductive members 3144.

In order to improve the cooling effect on the plurality of conductive members 3144, as a specific embodiment, the plurality of cooling pipes 3143b are provided in plurality, and the plurality of cooling pipes 3143b are provided at a one-to-one interval with the plurality of conductive members 3144. In the present embodiment, by providing the plurality of cooling pipes 3143b between the first fixing member 3141 and the second fixing member 3142, and disposing the plurality of cooling pipes 3143b at intervals from the plurality of conductive members 3144 one by one, after cooling air is introduced into each cooling pipe 3143b by the cooling machine 3143a, the cooling air in each cooling pipe 3143b can cool the conductive members 3144 more quickly and efficiently, thereby further improving the cooling effect on the conductive members 3144.

FIG. 10 illustrates a schematic of a structure of a core simulator in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application.

As shown in fig. 10, as a specific embodiment, the core simulator 312 includes a cartridge 3121, a first conductive element 3122 and a second conductive element 3123, the anode of the power source 313, the conductive structure 314, the first conductive element 3122 and the input end of the cartridge 3121 are sequentially connected, the cathode of the power source 313, the conductive structure 314, the second conductive element 3123 and the output end of the cartridge 3121 are sequentially connected, and the cartridge 3121 is used to generate heat energy under the effect of electric current.

It is to be understood that the first conductive element 3122 and the second conductive element 3123 may be copper bars, copper braids, aluminum or other conductive members 3144 with conductive functions, such as polymer conductive materials, conductive rubber, conductive plastics, and the like.

In the present embodiment, by sequentially connecting the positive electrode of the power supply 313, the conductive structure 314, the first conductive element 3122 and the input end of the cartridge 3121, and sequentially connecting the negative electrode of the power supply 313, the conductive structure 314, the second conductive element 3123 and the output end of the cartridge 3121, a current loop is formed between the power supply 313 and the core simulator 312, so that the cartridge 3121 can release heat under the action of current, and the simulation effect of the nuclear reactor is achieved.

As a specific embodiment, the first conductive element 3122 and the second conductive element 3123 may be in communication with the water supply module 100, so that cooling water is introduced into the first conductive element 3122 and the second conductive element 3123 through the water supply module 100, thereby cooling the first conductive element 3122 and the second conductive element 3123, and preventing the first conductive element 3122 and the second conductive element 3123 from influencing current conduction or even short-circuiting due to self-heating during the conduction.

With continued reference to fig. 10, as a specific embodiment, the heat release element 3121 includes a first conductive component 3121a, a second conductive component 3121b, and an isolation component 3121c and at least two heat generating components 3121d disposed between the first conductive component 3121a and the second conductive component 3121b, the isolation component 3121c being disposed between the two heat generating components 3121d and penetrating the second conductive component 3121b to divide the second conductive component 3121b into an input end and an output end which are insulated from each other, the input end of the second conductive component 3121b being connected to the first conductive element 3122, and the output end of the second conductive component 3121b being connected to the second conductive element 3123.

It is understood that the number of heat generating components 3121d on both sides of the isolation component 3121c may be plural, for example, in the cartridge 3121, three heat generating components 3121d are provided on one side of the isolation component 3121c, and two heat generating components 3121d are provided on the other side of the isolation component 3121 c.

The isolation member 3121c may be made of an insulating material such as quartz, glass, or the like; the heat generating component 3121d may be any material having a galvanic heating effect, such as a metallic conductive material, e.g., platinum, tungsten, nickel-based alloy, or a non-metallic material, e.g., silicon carbide, zirconia, and is within the scope of the present application.

In the present embodiment, the second conductive member 3121b is partitioned by the partition member 3121c into an input end and an output end insulated from each other, and thus, a current flows in from the input end of the second conductive member 3121b, flows through the heat generating member 3121d corresponding to the input end of the second conductive member 3121b, the heat generating member 3121d corresponding to the first conductive member 3121a and the output end of the second conductive member 3121b in order, and finally flows out from the output end of the second conductive member 3121b, thereby forming a current loop in the heat release element 3121, and generates heat energy at the heat generating member 3121d in the current loop, thereby realizing the simulation of the nuclear reactor.

As a specific embodiment, when the plurality of heat generating components 3121d are provided on both sides of the isolation component 3121c, the heat release element 3121 further includes at least two positioning spacers respectively provided on the heat generating components 3121d on both sides of the isolation component 3121c to isolate the plurality of heat generating components 3121d to maintain a space between the adjacent two heat generating components 3121d to ensure that the heat release element 3121 is not deformed by external force or non-inertial force in motion.

As a specific embodiment, the heat generating component 3121d has a structure distribution with a thin middle and thick two ends, so that the heat generating power at the middle position of the heat generating component 3121d is highest in the process of generating heat, and gradually decreases in the process of extending to the two ends, and cosine distribution of the heat generating power is realized, thereby realizing simulation with a nuclear reactor to a greater extent.

Thermal components fig. 11 illustrates a schematic of a drive module in a simulation system for a nuclear reactor thermodynamic and hydraulic test provided in some embodiments of the present application.

As shown in fig. 11, as a specific embodiment, the driving module 400 includes a motion data generating unit 410, a state control unit 420, and an action control unit 430 connected in sequence, the motion data generating unit 410 is used for generating motion data and transmitting the motion data to the state control unit 420, the state control unit 420 is used for generating a motion signal of the workbench 500 and transmitting the motion signal to the action control unit 430, and the action control unit 430 is used for driving the workbench 500 to move according to the motion signal of the workbench 500.

The motion data generating unit 410 may be a motion spectrum generator, which is a signal generator that generates motion data according to the effects of wind, waves, and swim of different levels of the simulation system.

In this embodiment, the motion data generating unit 410 may generate motion data according to an actual situation and send the motion data to the state control unit 420, the state control unit 420 may generate a motion signal of the workbench 500 according to the motion data in combination with a state of the test simulation subsystem and send the motion signal to the motion control unit 430, and the motion control unit 430 may drive the motion structure 520 in the workbench 500 to generate motion with at least two degrees of freedom according to the received motion signal of the workbench 500, so as to drive the reactor simulation subsystem to generate motion with at least two degrees of freedom, thereby simulating a real state of the nuclear reactor under the influence of transient external force, and analyzing the thermodynamic and hydraulic characteristics of the reactor simulation subsystem by detecting an actual flow change of the reactor simulation subsystem during the motion, thereby achieving research and analysis on the thermodynamic characteristics of the nuclear reactor under the effect of transient external force and ensuring reliability of research results.

With continued reference to fig. 11, as a specific embodiment, the test simulation subsystem further includes a parameter control module 600, where the parameter control simulation is connected to the state control unit 420, and the parameter control module 600 is connected to the flow detection module 200.

It can be understood that various other parameter detection devices, such as a temperature detector, a pressure detector, etc., are further disposed in the reactor simulation subsystem, and the parameter control module 600 is further connected with the parameter detection devices, such as the temperature detector, the pressure detector, etc., so as to integrate various parameters in the reactor simulation subsystem, thereby realizing centralized control of the parameters.

In this embodiment, the parameter control module 600 receives the actual flow change in the reactor simulation subsystem detected by the flow detection module 200 and sends the actual flow change to the state control unit 420, so that the movement signal of the workbench 500 generated by the state control unit 420 uses the flow parameter change in the reactor simulation subsystem as a reference to a certain extent, and the workbench 500 is controlled to drive the reactor simulation subsystem to move under the premise of ensuring the normal operation and safety of the reactor simulation subsystem, so that the state of the workbench 500 when driving the reactor simulation subsystem to move is close to the state of the nuclear reactor under the influence of transient external force, thereby improving the reliability of the research result of the thermal hydraulic characteristic of the nuclear reactor under the influence of the transient external force.

In order to reduce the time difference between the parameter control module 600 and the state control unit 420, so that the parameter control module 600 and the state control unit 420 are synchronized as much as possible, as a specific embodiment, the reactor simulation subsystem further comprises a synchronization controller, the synchronization controller is connected between the parameter control module 600 and the state control unit 420, the parameter control module 600 sends a signal to the state control unit 420 through the synchronization controller, so that the signal transmission time is reduced as much as possible, the parameter control module 600 and the state control unit 420 are synchronized as much as possible, and therefore, the state that the workbench 500 drives the reactor simulation subsystem to move is closer to the state of the nuclear reactor under the influence of transient external force, and the reliability of research results is improved.

With continued reference to fig. 11, as a specific embodiment, the motion control unit 430 includes a control subunit 431 and a driving subunit 432 connected to the control subunit 431, where the control subunit 431 is connected to the state control unit 420, and the driving unit is connected to the workbench 500, and the control subunit 431 is configured to receive the motion signal of the workbench 500 generated by the state control unit 420 and control the driving unit according to the motion signal of the workbench 500, so that the driving unit can drive the workbench 500 to move.

The control subunit 431 may be a servo control subunit 431, where the servo control subunit 431 is a controller integration for effectively controlling the position, speed, acceleration, and other variables of the object motion; the driving subunit 432 may adopt a hydraulic driving mode, or may participate in a pneumatic driving mode, an electric driving mode, or the like, and the driving subunit 432 may be various driving devices such as a driving motor, a driving cylinder, or the like.

In the foregoing, only the specific embodiments of the present application are described, and it will be clearly understood by those skilled in the art that, for convenience and brevity of description, the specific working processes of the systems, modules and units described above may refer to the corresponding processes in the foregoing method embodiments, which are not repeated herein. It should be understood that the scope of the present application is not limited thereto, and any person skilled in the art can easily conceive various equivalent modifications or substitutions within the technical scope of the present application, which are intended to be included in the scope of the present application.

Claims

1. A simulation system for a thermal hydraulic test of a nuclear reactor, comprising:

the test simulation subsystem comprises a water supply module, a flow detection module and a reactor simulation module, wherein the reactor simulation module comprises a simulation reactor and a heat exchange unit, at least part of the heat exchange unit is arranged in the simulation reactor, the water supply module is connected with the simulation reactor through the flow detection module, the water supply module is also connected with the heat exchange unit through the flow detection module, and the flow detection module is used for detecting actual flow change between the water supply module and the reactor simulation module;

The environment simulation subsystem comprises a driving module and a workbench connected with the driving module, the test simulation subsystem is installed on the workbench, and the driving module is used for driving the workbench and driving the test simulation subsystem to move in at least two degrees of freedom.

2. The simulation system of claim 1 wherein the heat exchange unit comprises a steam subunit and a condensing subunit in communication with each other, the steam subunit being disposed inside the simulation reactor, the steam subunit being in communication with the feedwater module through the flow detection module, the condensing subunit being in communication with the feedwater module through the flow detection module.

3. A simulation system according to claim 1, wherein the reactor simulation module further comprises a pressure stabilizing unit, one end of the pressure stabilizing unit is connected with the water supply module through the flow detection module, and the other end of the pressure stabilizing unit is connected with the simulated reactor.

4. A simulation system according to any one of claims 1 to 3, wherein the flow detection module comprises a plurality of detection units, and the plurality of detection units are arranged on a plurality of flow pipes on one side of the water supply module, which is close to the reactor simulation module, in a one-to-one correspondence manner.

5. The simulation system of claim 4, wherein the detection unit comprises:

the throttling structure is arranged on a flow pipeline of one side of the water supply module, which is close to the reactor simulation module;

the first detection branch is communicated between the upstream end and the downstream end of the throttling structure and is used for detecting the pressure difference in the throttling structure;

the second detection branch is communicated between the upstream end and the downstream end of the throttling structure and is used for detecting an external force influence factor in the throttling structure;

the processing subunit is respectively connected with the first detection branch and the second detection branch and is used for calculating and obtaining the actual flow change of the throttling structure according to the pressure difference and the external force influence factor in the throttling structure.

6. The simulation system of claim 5 wherein the second detection branch comprises a first shut-off valve, a first detection member, and a second shut-off valve in communication in sequence, the first shut-off valve in communication with the upstream end of the throttling structure, the second shut-off valve in communication with the downstream end of the throttling structure, and the first detection member in communication with the processing subunit.

7. The simulation system of claim 1, wherein the simulation reactor comprises a reactor body, a reactor core simulator arranged in the reactor body, a power supply and at least two conductive structures, wherein the anode of the power supply, the reactor core simulator and the cathode of the power supply are sequentially connected through the two conductive structures, the reactor core simulator, the flow detection module and the water supply module are sequentially communicated, the reactor core simulator is used for generating heat energy under the action of current of the power supply, the conductive structures are used for cooling the heat generated by the current in the conductive process while conducting electricity, and at least part of the heat exchange units are arranged in the reactor body so as to utilize the heat energy generated by the reactor core simulator.

8. The modeling system of claim 7, wherein the conductive structure comprises a first fixture, a second fixture, and a cooling member and a plurality of conductive members connected between the first and second fixtures, the first fixture being connected to a positive or negative pole of the power supply, the second fixture being connected to the core simulator, the cooling member being configured to cool the conductive members during the electrical conduction.

9. The simulation system of claim 8 wherein the conductive structure further comprises an insulating member surrounding each conductive member, the insulating member having a plurality of openings therein exposing at least a portion of the conductive members to enhance cooling.

10. The simulation system according to claim 9, wherein the cooling member comprises a cooling machine and a cooling pipe which are communicated with each other, the cooling pipe is connected between the first fixing member and the second fixing member, a plurality of flow holes are formed in the cooling pipe, the cooling machine is used for inputting cooling gas into the cooling pipe, and the flow holes are used for enabling the cooling gas in the cooling pipe to flow to the opening of each conductive member.

11. The simulation system according to claim 10, wherein the number of the cooling pipes is plural, and the plural cooling pipes are arranged at a one-to-one interval with the plural conductive members.

12. The simulation system of claim 7 wherein the core simulator comprises a cartridge, a first conductive element and a second conductive element, the positive electrode of the power supply, the conductive structure, the first conductive element and the input of the cartridge being connected in sequence, the negative electrode of the power supply, the conductive structure, the second conductive element and the output of the cartridge being connected in sequence, the first conductive element and the second conductive element further being in communication with the feedwater module through the flow detection module, the cartridge being configured to generate thermal energy under the influence of an electrical current.

13. A simulation system according to claim 12, wherein the cartridge comprises a first conductive member, a second conductive member, and a spacer member and at least two heat generating members disposed between the first conductive member and the second conductive member, the spacer member being disposed between the two heat generating members and extending through the second conductive member to divide the second conductive member into an input end and an output end that are insulated from each other, the input end of the second conductive member being connected to the first conductive element, the output end of the second conductive member being connected to the second conductive element.

14. A simulation system according to claim 1, wherein the driving module comprises a motion data generating unit, a state control unit and an action control unit which are sequentially connected, the motion data generating unit is used for generating motion data and sending the motion data to the state control unit, the state control unit is used for generating a workbench motion signal and sending the motion signal to the action control unit, and the action control unit is used for driving the workbench to move according to the workbench motion signal.