CN112927828A - Nuclear power station pipeline leakage simulation test system and method - Google Patents
Nuclear power station pipeline leakage simulation test system and method Download PDFInfo
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- CN112927828A CN112927828A CN202110083167.9A CN202110083167A CN112927828A CN 112927828 A CN112927828 A CN 112927828A CN 202110083167 A CN202110083167 A CN 202110083167A CN 112927828 A CN112927828 A CN 112927828A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/002—Detection of leaks
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to a simulation test system and a method for nuclear power station pipeline leakage, wherein the simulation test system comprises: the device comprises a pipeline simulation device, a heating device, a leakage simulation device, a collection device and an upper computer; the upper computer is used for receiving a simulation test instruction input by a user and acquiring heating state information and leakage state information; according to the heating state information, the heating power of the heating pipe is adjusted through the power adjusting cabinet, so that the detected temperature of the pipeline reaches the temperature of the pipeline of the nuclear power station under the normal operation working condition; controlling the medium generating device to output the medium of the corresponding type and adjusting the opening of the adjusting valve according to the leakage state information; and the device is also used for acquiring the medium temperature and humidity information in real time and determining a medium temperature and humidity response curve corresponding to the current simulation test instruction according to the medium temperature and humidity information. By implementing the technical scheme of the invention, different leakage working conditions at the welding line of the pipeline of the nuclear power station can be simulated, so that the change of the detection signal of the temperature and humidity sensor under the influence of different factors can be obtained.
Description
Technical Field
The invention relates to the field of nuclear power, in particular to a nuclear power station pipeline leakage simulation test system and method.
Background
During the power operation of the nuclear power station, after leakage of a primary circuit pressure boundary in a reactor plant occurs, high-temperature and high-pressure fluid is subjected to flash evaporation at a leakage source to form flash evaporation gas and is diffused. Taking a reactor coolant system as an example, the process of leaking a pipeline into a containment vessel by a through-wall crack can be roughly divided into four physical processes:
1. critical flow process at the break;
2. the diffusion process of the water vapor between the inner wall of the heat preservation layer and the outer wall of the pipeline;
3. the steam passes through the heat-insulating layer and enters the equipment compartment and the containment space in a diffusion process;
4. the liquid state directly enters the pit, and the wet air is condensed into liquid water in the surface of the cooling coil.
After the leakage of the main steam pipeline of the two loops occurs, the second-stage physical process, namely the diffusion process of the water vapor between the inner wall of the heat insulation layer and the outer wall of the pipeline, is directly carried out.
Leak monitoring for the second stage: due to the molecular thermal motion and the kinetic energy of initial injection, water vapor can diffuse in a gap between the pipeline and the heat insulation layer, so that the humidity and the temperature change are brought, and the water vapor penetrates through the heat insulation layer and then diffuses into the containment vessel to change the humidity. Therefore, whether leakage occurs can be determined by monitoring the change in temperature and humidity. However, there are several reasons that affect the reliability and safety of detection, including, for example:
1. the pipelines to be checked are horizontally arranged, vertically arranged and obliquely arranged, and different types of arrangement cause different flow directions of water vapor between the inner wall of the heat preservation layer and the outer wall of the pipeline;
2. gaps between adjacent heat-insulating layers (because the heat-insulating layers are formed by assembling three heat-insulating boxes, gaps exist between the adjacent heat-insulating boxes), the leakage propagation flow direction of water vapor can be changed, and the feasibility of detection is influenced;
3. the maximum flow, flow speed and temperature of the leakage can damage the sensitive elements of the probe, and the safety of the probe is influenced;
4. the medium of the first loop is high-temperature and high-pressure water, the medium of the second loop is high-temperature and high-pressure steam, and different types of media have different performances on signals detected by the humidity of the probe;
5. under different working conditions, the temperature and the pressure of the medium are different, and the signal change detected by the humidity of the medium probe with different physical parameters has different expressions;
6. the sizes of the cracks are different, the leakage flow is different, and the signal change detected by the humidity has different expressions;
7. on the pipeline axis, at different leakage positions in the circumferential direction, the signal change detected by the humidity has different performances.
In order to study different performances of signal changes detected by the temperature and humidity probe under the influence of the above different factors, a set of test device needs to be designed for verification.
Disclosure of Invention
The invention aims to solve the technical problem of providing a nuclear power station pipeline leakage simulation test system and method aiming at the defects in the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows: a nuclear power station pipeline leakage simulation test system is constructed, and the system comprises: the device comprises a pipeline simulation device, a heating device, a leakage simulation device, a collection device and an upper computer; wherein the content of the first and second substances,
the pipe simulation apparatus includes: a main simulation pipeline for simulating a pipeline of a nuclear power station; the heat insulation layer is sleeved on the periphery of the main simulation pipeline; a support for supporting the main simulated duct;
the heating device includes: the heating pipes are dispersedly arranged on the inner wall of the main simulation pipeline; the power adjusting cabinet is used for adjusting the heating power of the heating pipe;
the leakage simulation apparatus includes: a media generating device for generating different types of media; the regulating valve is arranged on an output port of the medium generating device; the nozzles are dispersedly arranged on the circumference or the half circumference of the main simulation pipeline and sequentially penetrate through the pipe wall of the main simulation pipeline and the heat preservation layer from the inside of the main simulation pipeline; a plurality of delivery conduits connecting the regulating valve with respective nozzles;
the collection device comprises: the temperature and humidity sensors are dispersedly arranged on the periphery of the heat insulation layer along the axis direction of the main simulation pipeline; the temperature detection modules are arranged in a scattered manner along the axial direction of the main simulation pipeline, and each group of temperature detection modules comprises a plurality of thermocouples which are arranged on the inner/outer wall of the main simulation pipeline in a scattered manner along the circumferential direction of the main simulation pipeline; the acquisition module is used for processing the pipeline temperature information detected by the thermocouple and the medium temperature and humidity information detected by the temperature and humidity sensor;
the upper computer is used for receiving a simulation test instruction input by a user and acquiring corresponding heating state information and leakage state information according to the simulation test instruction; according to the heating state information, the heating power of the heating pipe is adjusted through the power adjusting cabinet, so that the detected temperature of the pipeline reaches the temperature of the pipeline of the nuclear power station under the normal operation working condition; controlling the medium generating device to output the medium of the corresponding type and adjusting the opening of the corresponding adjusting valve according to the leakage state information; and the device is also used for acquiring medium temperature and humidity information from the acquisition module in real time and determining a medium temperature and humidity response curve corresponding to the current simulation test instruction according to the medium temperature and humidity information.
Preferably, the upper computer is further configured to determine a temperature and humidity threshold value and response time according to the medium temperature and humidity response curve.
Preferably, the upper computer is further configured to establish a medium leakage model according to the medium temperature and humidity information corresponding to the plurality of simulation test instructions.
Preferably, the upper computer is further configured to determine a model selection, an installation mode and an arrangement scheme of the temperature and humidity sensor under the normal operation condition of the nuclear power plant pipeline according to the medium temperature and humidity information corresponding to the plurality of simulation test instructions; wherein the plurality of simulated test instructions include different heating state information and/or leakage state information.
Preferably, the number of the nozzles is five, and one nozzle is arranged at 45 degrees intervals on the right semi-circumference of the same section of the main simulated pipeline.
Preferably, a temperature and humidity sensor is arranged at intervals of 550mm at the periphery of the heat insulation layer along the axial direction of the main simulation pipeline.
Preferably, a set of temperature detection modules is arranged at intervals of 550mm along the axis direction of the main simulated pipeline, and each set of temperature detection modules comprises:
four internal thermocouples arranged on the inner wall of the main simulation pipeline at intervals of 90 degrees in the circumferential direction of the main simulation pipeline;
four external thermocouples arranged on the outer wall of the main analog pipe at intervals of 90 degrees in the circumferential direction of the main analog pipe.
Preferably, 36 heating pipes are uniformly distributed on the inner wall of the main simulation pipeline.
Preferably, the acquisition module comprises:
the adapter box is used for summarizing the pipeline temperature information detected by the thermocouple;
the transmitter is used for processing the medium temperature and humidity information detected by the temperature and humidity sensor;
and the acquisition card is used for sending the quality temperature and humidity information processed by the transmitter and the pipeline temperature information processed by the adapter box into the upper computer.
The invention also constructs a simulation test method for the pipeline leakage of the nuclear power station, and the method comprises the following steps in the upper computer of the simulation test system for the pipeline leakage of the nuclear power station:
receiving a simulation test instruction input by a user, and acquiring corresponding heating state information and leakage state information according to the simulation test instruction;
according to the heating state information, the heating power of the heating pipe is adjusted through the power adjusting cabinet, so that the temperature of the pipeline detected by the thermocouple reaches the temperature of the pipeline of the nuclear power station under the normal operation working condition;
controlling a medium generating device to output a medium of a corresponding type and adjusting the opening of a corresponding adjusting valve according to the leakage state information;
and acquiring medium temperature and humidity information from an acquisition module in real time, and determining a medium temperature and humidity response curve corresponding to the current simulation test instruction according to the medium temperature and humidity information.
According to the technical scheme provided by the invention, different leakage working conditions at the welding line of the pipeline of the nuclear power station can be simulated by designing a set of system and method for simulating the leakage of the pipeline of the nuclear power station, so that the change of the detection signal of the temperature and humidity sensor under the influence of different factors is obtained, and a basis is provided for the subsequent leakage monitoring, such as the type selection of the sensor, the installation mode, the arrangement scheme and the like.
Drawings
In order to illustrate the embodiments of the invention more clearly, the drawings that are needed in the description of the embodiments will be briefly described below, it being apparent that the drawings in the following description are only some embodiments of the invention, and that other drawings may be derived from those drawings by a person skilled in the art without inventive effort. In the drawings:
FIG. 1 is a block diagram of a simulation test system for pipeline leakage in a nuclear power plant according to a first embodiment of the present invention;
FIG. 2A is a cross-sectional view of a nuclear power plant pipeline leakage simulation test system according to a second embodiment of the present invention, taken along the axis of a main simulation pipeline;
fig. 2B is a cross-sectional view of a pipe leakage simulation test system for a nuclear power plant according to a second embodiment of the present invention, taken along a cross-sectional direction of a main simulation pipe;
FIG. 3 is a schematic installation diagram of a leakage simulation apparatus of a nuclear power plant pipeline leakage simulation test system according to a third embodiment of the present invention;
FIG. 4A is a cross-sectional view of a nuclear power plant pipeline leakage simulation test system according to a third embodiment of the present invention, taken along the axis of a main simulation pipeline;
fig. 4B is a cross-sectional view of a pipe leakage simulation test system for a nuclear power plant according to a third embodiment of the present invention, taken along a cross-sectional direction of a main simulation pipe;
FIG. 5 is a schematic structural diagram of a simulation test system for pipeline leakage in a nuclear power plant according to a fourth embodiment of the present invention;
FIG. 6 is a schematic diagram of a host computer display interface according to the present invention;
fig. 7 is a flowchart of a simulation test method for nuclear power plant pipeline leakage according to a fifth embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
In order to research the influence of different factors on signals detected by the temperature and humidity sensor, the nuclear power station pipeline leakage simulation test system is constructed to simulate the change of temperature and humidity signals under the influence of different factors, and provide a basis for sensor model selection (highest temperature and humidity), a sensor installation mode and sensor arrangement for subsequent leakage monitoring.
Fig. 1 is a structural diagram of a first embodiment of a simulation test system for nuclear power plant pipeline leakage according to the present invention, the simulation test system including: pipeline analogue means, heating device, leakage analogue means, collection system and host computer.
Wherein the content of the first and second substances,
the pipe simulation apparatus includes a main simulation pipe 11, an insulation layer 12, and a bracket (not shown). The main simulated pipe 11 is used for simulating a nuclear power plant pipe, that is, a section of pipe designed and processed by simulating the size, shape, and weld position of the nuclear power plant pipe. The bracket is used for supporting the main simulation pipeline 11, and the main simulation pipeline 11 can be horizontally arranged or vertically arranged under the support of the bracket. The heat insulation layer 12 is sleeved on the periphery of the main simulated pipeline 11 and used for ensuring the temperature parameters of the main simulated pipeline 11, namely, the heat insulation layer is a set of heat insulation box and installation accessories which are designed and processed by simulating the size, shape, structure and heat insulation performance parameters of the heat insulation layer of the nuclear power station pipeline.
The heating device comprises a power adjusting cabinet 22 and a plurality of heating pipes 21, wherein the plurality of heating pipes 21 are dispersedly arranged on the inner wall of the main simulated pipeline 11; the power regulating cabinet 22 is used for regulating the heating power of the heating pipe 21. For example, a circle of U-shaped heating pipes is uniformly arranged on the inner wall of the main simulated pipeline 11, and a corresponding electric cabinet and a power adjusting cabinet are configured. The power regulating cabinet is used for regulating the power of the heating device by regulating the power supply current of the heating pipe, so that the temperature of the main simulation pipeline 11 reaches the temperature of the normal operation working condition of the nuclear power station pipeline.
The leakage simulation device comprises a medium generating device 31, a regulating valve 34, a plurality of nozzles 32 (only one shown in the figure), a plurality of delivery ducts 33 (only one shown in the figure). The medium generating device 31 is used for generating different types of media, such as high-temperature high-pressure water and steam for generating actual working temperature and pressure parameters of a nuclear power station pipeline; the regulating valve 34 is arranged on the output port of the medium generating device 31; the plurality of nozzles 32 are dispersedly arranged on the circumference or the half circumference of the main simulated pipeline 11, and sequentially penetrate through the pipe wall of the main simulated pipeline 11 and the heat preservation layer 12 from the inside of the main simulated pipeline 11; the delivery conduits 33 connect the regulating valves 34 with the respective nozzles 32 (it being understood that one test example would only connect one delivery conduit with a regulating valve). In addition, different delivery pipelines 33 can be replaced outside the device according to actual test requirements, so that nozzles 32 connected with the delivery pipelines can be replaced with different calibers, and different leakage conditions can be simulated by controlling the flow rates of water and steam and the calibers of the nozzles 32 connected to the main simulation pipeline.
The acquisition device comprises a plurality of temperature and humidity sensors 41, a plurality of temperature detection modules and an acquisition module 43, wherein the temperature and humidity sensors 41(001MZ, 002MZ, 003MZ and 004MZ) are dispersedly arranged on the periphery of the thermal insulation layer 12 along the axial direction of the main analog pipeline 11; the plurality of groups of temperature detection modules are dispersedly arranged along the axial direction of the main simulated pipeline 11, each group of temperature detection modules comprises a plurality of thermocouples 42, and the thermocouples 42 are dispersedly arranged on the inner/outer wall of the main simulated pipeline 11 along the circumferential direction of the main simulated pipeline 11; the acquisition module 43 is used for processing the pipeline temperature information detected by the thermocouple and the medium temperature and humidity information detected by the temperature and humidity sensor, that is, acquiring test data under various leakage conditions, and sending the test data to the upper computer for further analysis and processing.
The upper computer (not shown) is used for receiving a simulation test instruction input by a user and acquiring corresponding heating state information and leakage state information according to the simulation test instruction; moreover, according to the heating state information, the heating power of the heating pipe 21 is adjusted through the power adjusting cabinet 22, so that the detected temperature of the pipeline reaches the temperature of the pipeline of the nuclear power station under the normal operation working condition; controlling the medium generating device 31 to output the corresponding type of medium and adjust the opening of the corresponding adjusting valve 34 according to the leakage state information; and is further configured to obtain the medium temperature and humidity information in real time from the acquisition module 43, and determine a medium temperature and humidity response curve corresponding to the current simulation test instruction according to the medium temperature and humidity information.
The nuclear power station pipeline leakage simulation test system of the embodiment can simulate the response curve of the temperature and humidity sensor when the welding seam of the nuclear power station pipeline is at different circumferential angles and different leakage rates on the same cross section.
Further, the upper computer can also perform at least one of the following analysis processes: determining a temperature and humidity threshold value and response time according to the obtained medium temperature and humidity response curve; establishing a medium leakage model according to medium temperature and humidity information respectively corresponding to the plurality of simulation test instructions; determining the type selection, the installation mode and the arrangement scheme of the temperature and humidity sensor under the normal operation working condition of the nuclear power station pipeline according to the medium temperature and humidity information corresponding to the plurality of simulation test instructions respectively; wherein the plurality of simulated test instructions include different heating state information and/or leakage state information.
In a specific embodiment, referring to fig. 2A and 2B, the main analog pipe 11 is horizontally disposed, and one temperature and humidity sensor is disposed at a distance of 550mm at the periphery of the thermal insulation layer 12 along the axial direction of the main analog pipe 11, that is, a total of four temperature and humidity sensors 001MZ, 002MZ, 003MZ, 004MZ are disposed to monitor the leaked medium. Meanwhile, a group of temperature detection modules are arranged at intervals of 550mm along the axis direction of the main simulated pipeline, namely, four groups of temperature detection modules are arranged. Each group of temperature detection modules comprises four internal thermocouples and four external thermocouples, wherein the four internal thermocouples are arranged on the inner wall of the main simulated pipeline at intervals of 90 degrees along the circumferential direction of the main simulated pipeline; four external thermocouples were disposed on the outer wall of the main simulated pipe at intervals of 90 degrees in the circumferential direction of the main simulated pipe. That is, a total of 32 thermocouples were provided to monitor the temperature of the inner and outer walls of the main simulated duct 11, as shown in detail in FIG. 6, which includes 16 external thermocouples (only thermocouples 001MT-004MT, 005MT-008MT, 009MT-012MT are shown in the figure) and 16 internal thermocouples. In addition, 36 heating pipes (not shown) are uniformly distributed on the inner wall of the main simulated pipeline, and the 36 heating pipes are used for heating the inner wall of the main simulated pipeline 11 so as to simulate the temperature of the pipe wall under the normal operation condition of the nuclear power plant pipeline. On the right semi-circumference of the cross section at AA of the main simulated duct 11, one nozzle 32 is provided at every 45 degrees, i.e., five nozzles are provided at the 0 °, 45 °, 90 °, 135 °, 180 ° positions of the circumference, respectively.
Further, referring to fig. 3, through holes for the nozzles 32 to extend out are dispersedly formed (at 45 ° intervals) on the right half circumference of the AA cross section of the main analog pipe 11, the nozzles 32 are connected to the main analog pipe 11 by a ferrule 35, the lower end of the ferrule is communicated with one end of the corresponding delivery pipe 33, and the other end of the delivery pipe 33 is connected to the medium generating device through an external hose 36. By adjusting the opening of the corresponding valve (not shown) and replacing the nozzles 32 of different diameters, different leakage rates can be simulated. In addition, can be convenient in the heat preservation outside, be fit for changing 5 different pipeline under the environment that operating personnel can reach, realize that 5 different medium of upwards nozzle 32 of week spout and put.
In another specific embodiment, with reference to fig. 4A and 4B, the pipe leakage simulation test system of the nuclear power plant of this embodiment differs from the embodiment shown in fig. 2A and 2B only in that: the main analog pipeline 11 is vertically arranged, and other similar places are not described in detail herein.
In an optional embodiment, the acquisition module specifically includes an acquisition card 431, a transmitter 432, and a junction box 433, where the junction box 433 is configured to perform summary processing on the pipe temperature information detected by the thermocouple; the transmitter 432 is used for processing medium temperature and humidity information detected by the temperature and humidity sensor; the acquisition card 431 is used for sending the temperature and humidity information of the mass processed by the transmitter 432 and the temperature information of the pipeline processed by the adapter 433 to the upper computer 50, for example, the acquisition card 431 may be inserted into the upper computer 50 through a PXI interface. In this embodiment, after each temperature and humidity sensor is installed, the signals collected by the temperature and humidity sensor are input to the transmitter 432 through the extension line, and the temperature and humidity signals are converted by the transmitter 432 and then input to the acquisition card 431. The thermocouple for measuring the temperature of the main simulation pipeline is directly connected to the adapter 433 with temperature compensation, then input into the acquisition card, and processed and operated by the upper computer 50, so that the temperature and humidity values of corresponding detection points can be displayed in real time. The upper computer 50 acquires and displays the interface as shown in fig. 6.
Further, the upper computer can realize the leakage simulation of different angles, different pressures and different leakage rates on the circumference through a plurality of times of simulation tests, namely, changing variables in the simulation test instruction, and acquiring the corresponding medium temperature and humidity response curves during each simulation test. Finally, a medium leakage model can be established as shown in equation 1:
Leak(t)＝fL(Spi，Tpi,Ac，Lis，Ad，Pst，P，T，Q，CLt) formula 1
Wherein S ispiSimulating the external dimension of the pipeline for the main model, wherein the external dimension is generally a fixed value; t ispiSimulating the surface temperature of the pipeline for the main model; a. thecCircumferential angles of 5 different nozzles; l isisThe gap between adjacent heat-insulating layers is generally a fixed value; a. thedSimulating the inclination of the duct for the main model, including 0 degrees (horizontal) and 90 degrees (vertical); pstThe leakage change on the axis is related to the installation positions of the four temperature and humidity sensors; p is the pressure of the cooling medium and can be adjusted by an adjusting valve; t is the temperature of the cooling medium and can be adjusted by adjusting the power of the heating pipe; q is the mass flow of the cooling medium, can be adjusted through a regulating valve, and can be measured by a mass flowmeter; cLThe type of cooling medium comprises water and steam; and t is leakage time, and time can be recorded during continuous collection.
During simulation test, the power of the heating pipe is regulated to make the temperature of the pipe detected by the thermocouple reach the temperature of the pipe in the normal operation condition, the medium generator is made to discharge high temperature and high pressure water, the nozzle in corresponding angle is selected, the opening of the regulating valve is regulated to simulate the leakage of the pipe welding seam in different angles, different pressures and different leakage rates, and the response curve of the temperature and humidity sensor is obtained from the collecting module and the corresponding response time and threshold are obtained. And then, replacing the spraying medium with high-pressure steam, selecting a nozzle with a corresponding circumferential angle by adjusting the power of the heating pipe, adjusting the opening of the adjusting valve to simulate leakage of the pipeline welding seam of the nuclear power station at different angles, different pressures and different leakage rates on the circumference, acquiring a response curve of the temperature and humidity sensor from the acquisition module, and acquiring corresponding response time and threshold values.
The system of the embodiment is used for simulation test, the influence of the 11 variables (2 fixed variables and 9 variable variables) can be verified, and the working environment (temperature, humidity and pressure), the installation mode and the arrangement scheme of the temperature and humidity sensor for engineering and the feasibility of the temperature and humidity measurement leakage principle are determined.
Fig. 7 is a flowchart of a simulation test method for nuclear power plant pipeline leakage according to a fifth embodiment of the present invention, where the simulation test method for nuclear power plant pipeline leakage according to the embodiment is applied to the upper computer of the simulation test system for nuclear power plant pipeline leakage according to the above embodiment, and includes the following steps:
s10, receiving a simulation test instruction input by a user, and acquiring corresponding heating state information and leakage state information according to the simulation test instruction;
s20, adjusting the heating power of a heating pipe through a power adjusting cabinet according to the heating state information so that the temperature of the pipeline detected by the thermocouple reaches the temperature of the pipeline of the nuclear power station under the normal operation working condition;
s30, controlling a medium generating device to output a medium of a corresponding type and adjusting the opening of a corresponding adjusting valve according to the leakage state information;
and S40, acquiring medium temperature and humidity information from the acquisition module in real time, and determining a medium temperature and humidity response curve corresponding to the current simulation test instruction according to the medium temperature and humidity information.
Specifically, with reference to fig. 2A and 2B or fig. 4A and 4B, firstly, the inner wall of the main simulation pipeline with the external insulating layer is heated by controlling the heating pipe, and whether the temperature reaches the normal operating temperature of the nuclear power plant pipeline is detected by the thermocouple, so that the operating condition of the main pipeline of the nuclear power plant is truly simulated. And then, the leakage working condition of the nuclear power station pipeline can be truly simulated through the conveying pipeline pre-arranged in the main simulation pipeline and the nozzle tightly attached to the main simulation pipeline. And, through the arrangement of 5 nozzles in the circumference direction, the leakage of the nuclear power station pipeline in different circumferential directions is simulated. Meanwhile, the detection capability, the sensitivity and the response time of the temperature and humidity sensors at different positions can be determined by 4 temperature and humidity sensors arranged on the axis.
In addition, different leakage rates can be simulated by replacing nozzles with different apertures and adjusting the opening of the adjusting valve; simulating the arrangement mode of the pipelines of the nuclear power station by simulating the horizontal and vertical arrangement of the pipelines of the nuclear power station; by injecting different types of media such as water and steam, simulating leakage media of a first loop (water) and a second loop (steam) of the nuclear power station; the temperature, pressure of the leaking medium can also be varied (e.g., 0.05gpm to 1gpm of leakage can be simulated by adjusting the valve opening).
And finally, the upper computer continuously collects and records the temperature and humidity information detected by the humidity sensor through the collection module, and generates a curve of the temperature and humidity changing along with time to obtain real temperature and humidity response corresponding to leakage.
The above description is only a preferred embodiment of the present invention and is not intended to limit the present invention, and various modifications and changes may be made by those skilled in the art. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the scope of the claims of the present invention.
Claims (10)
1. A nuclear power station pipeline leakage simulation test system is characterized by comprising: the device comprises a pipeline simulation device, a heating device, a leakage simulation device, a collection device and an upper computer; wherein the content of the first and second substances,
the pipe simulation apparatus includes: a main simulation pipeline for simulating a pipeline of a nuclear power station; the heat insulation layer is sleeved on the periphery of the main simulation pipeline; a support for supporting the main simulated duct;
the heating device includes: the heating pipes are dispersedly arranged on the inner wall of the main simulation pipeline; the power adjusting cabinet is used for adjusting the heating power of the heating pipe;
the leakage simulation apparatus includes: a media generating device for generating different types of media; the regulating valve is arranged on an output port of the medium generating device; the nozzles are dispersedly arranged on the circumference or the half circumference of the main simulation pipeline and sequentially penetrate through the pipe wall of the main simulation pipeline and the heat preservation layer from the inside of the main simulation pipeline; a plurality of delivery conduits connecting the regulating valve with respective nozzles;
the collection device comprises: the temperature and humidity sensors are dispersedly arranged on the periphery of the heat insulation layer along the axis direction of the main simulation pipeline; the temperature detection modules are arranged in a scattered manner along the axial direction of the main simulation pipeline, and each group of temperature detection modules comprises a plurality of thermocouples which are arranged on the inner/outer wall of the main simulation pipeline in a scattered manner along the circumferential direction of the main simulation pipeline; the acquisition module is used for processing the pipeline temperature information detected by the thermocouple and the medium temperature and humidity information detected by the temperature and humidity sensor;
the upper computer is used for receiving a simulation test instruction input by a user and acquiring corresponding heating state information and leakage state information according to the simulation test instruction; according to the heating state information, the heating power of the heating pipe is adjusted through the power adjusting cabinet, so that the detected temperature of the pipeline reaches the temperature of the pipeline of the nuclear power station under the normal operation working condition; controlling the medium generating device to output the medium of the corresponding type and adjusting the opening of the corresponding adjusting valve according to the leakage state information; and the device is also used for acquiring medium temperature and humidity information from the acquisition module in real time and determining a medium temperature and humidity response curve corresponding to the current simulation test instruction according to the medium temperature and humidity information.
2. The nuclear power plant pipe leak simulation test system according to claim 1,
and the upper computer is also used for determining a temperature and humidity threshold value and response time according to the medium temperature and humidity response curve.
3. The nuclear power plant pipe leak simulation test system according to claim 1,
and the upper computer is also used for establishing a medium leakage model according to the medium temperature and humidity information respectively corresponding to the plurality of simulation test instructions.
4. The nuclear power plant pipe leak simulation test system according to claim 1,
the upper computer is further used for determining the model selection, the installation mode and the arrangement scheme of the temperature and humidity sensor under the normal operation condition of the nuclear power station pipeline according to the medium temperature and humidity information respectively corresponding to the plurality of simulation test instructions; wherein the plurality of simulated test instructions include different heating state information and/or leakage state information.
5. The nuclear power plant pipeline leakage simulation test system according to claim 1, wherein the number of the nozzles is five, and one nozzle is provided at 45 degrees intervals on a right half circumference of the same cross section of the main simulation pipeline.
6. The nuclear power plant pipeline leakage simulation test system of claim 1, wherein a temperature and humidity sensor is arranged at every 550mm distance around the periphery of the insulating layer along the axis of the main simulation pipeline.
7. The nuclear power plant pipeline leakage simulation test system of claim 1, wherein a set of temperature detection modules is disposed at intervals of 550mm in the direction of the main simulated pipeline axis, and each set of temperature detection modules comprises:
four internal thermocouples arranged on the inner wall of the main simulation pipeline at intervals of 90 degrees in the circumferential direction of the main simulation pipeline;
four external thermocouples arranged on the outer wall of the main analog pipe at intervals of 90 degrees in the circumferential direction of the main analog pipe.
8. The nuclear power plant pipeline leakage simulation test system of claim 1, wherein 36 heating pipes are uniformly distributed on the inner wall of the main simulation pipeline.
9. The nuclear power plant pipeline leak simulation test system of claim 1, wherein the collection module comprises:
the adapter box is used for summarizing the pipeline temperature information detected by the thermocouple;
the transmitter is used for processing the medium temperature and humidity information detected by the temperature and humidity sensor;
and the acquisition card is used for sending the quality temperature and humidity information processed by the transmitter and the pipeline temperature information processed by the adapter box into the upper computer.
10. A simulation test method for nuclear power plant pipeline leakage, which is characterized in that the following steps are carried out in the upper computer of the simulation test system for nuclear power plant pipeline leakage according to any one of claims 1 to 9:
receiving a simulation test instruction input by a user, and acquiring corresponding heating state information and leakage state information according to the simulation test instruction;
according to the heating state information, the heating power of the heating pipe is adjusted through the power adjusting cabinet, so that the temperature of the pipeline detected by the thermocouple reaches the temperature of the pipeline of the nuclear power station under the normal operation working condition;
controlling a medium generating device to output a medium of a corresponding type and adjusting the opening of a corresponding adjusting valve according to the leakage state information;
and acquiring medium temperature and humidity information from an acquisition module in real time, and determining a medium temperature and humidity response curve corresponding to the current simulation test instruction according to the medium temperature and humidity information.
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