In-situ test device and method for simulating the surface boiling fouling of a pipe body of a reactor core flow channel

Abstract

The application discloses a kind of in-situ testing device and method of pipe body surface boiling fouling of analog core flow channel, device includes test section pipeline, several array arrangements are inserted and placed in the inside of pipeline tubular sample, and inner heating rod is arranged in tubular sample, tubular sample is threaded through the sealing element of pipeline two ends, and is connected with pressure regulating device at one end;Test section pipeline one side is opened along axial direction with several connecting holes, each connecting hole is connected with medium inlet pipeline, medium outlet pipeline and multiple sealing plugs respectively, sealing plug includes at least one visible sealing plug, visible sealing plug is equipped with laser signal transceiver outside and is connected with data processing system, and the window on visible sealing plug can be passed by laser emitted by laser signal transceiver and returned after being reflected by tubular sample.The device and method of the application have obvious advantages in the authenticity, flexibility and connection reliability of simulation condition, and can be fixed for long-term single test or quickly adjusted to adapt to different test purposes.

Description

Technical Field

[0001] This invention relates to the field of high-temperature corrosion research of metallic materials, and in particular to an in-situ testing device and method for testing boiling fouling on the surface of a tube simulating a reactor core flow channel. Background Technology

[0002] Inside the reactor core, the heart of a nuclear reactor, the fuel cladding tubes play a crucial role. They must withstand corrosion from high-temperature, high-pressure water and effectively conduct the enormous heat released by the nuclear reaction. However, during long-term operation, the cladding tubes face two major challenges: first, the reduced thermal conductivity due to fouling, which can cause the cladding tube temperature to rise and accelerate corrosion failure; and second, the accumulation of boron ions, which can cause localized reduced reactivity, leading to uneven axial power distribution. These phenomena have already triggered several reactor accidents. Therefore, accurately simulating the deposition behavior of corrosion products on the surface of the cladding tubes inside the reactor core is crucial for improving reactor operational safety and predicting the service life of the cladding.

[0003] Currently, there are three main methods for testing fouling in tubular materials: orifice accelerated deposition, electromagnetic heating deposition, and internal heating deposition. Orifice accelerated deposition accelerates flow by narrowing the flow channel, enabling rapid deposition of corrosion products. However, this method fails to consider the crucial fouling mechanism of surface supercooling and nucleation boiling, thus limiting its effectiveness. Electromagnetic heating deposition utilizes high-power electromagnetic fields to achieve nucleation boiling deposition. However, this method is only suitable for nickel-based alloys with moderate conductivity and is not applicable to zirconium alloy clad tubes. Furthermore, strong electromagnetic fields may interfere with the deposition process.

[0004] The internal heating deposition method uses an internal heating rod inside a tubular sample to induce a supercooled nucleation boiling state on the tube surface, while simultaneously introducing flowing high-temperature, high-pressure water to test the deposition behavior of corrosion products. Although this method is currently considered a superior testing technique, it still has some limitations. First, scale-induced accidents in actual reactor core operation often occur near the grid, and this method fails to account for scale deposition behavior under complex core flow conditions such as grid positioning, lateral turbulence, and flow-induced vibration. Second, all three existing methods can only be sampled and tested after the deposition experiment, making in-situ observation impossible, especially in obtaining real-time, online, and continuous deposition rate data.

[0005] Therefore, it is necessary to propose an in-situ testing device and method for simulating boiling fouling on the surface of the core flow channel to solve the above-mentioned technical problems, optimize the design of existing devices, improve testing flexibility and applicability, and ensure reactor safety and extend the life of the cladding tubes. Summary of the Invention

[0006] The purpose of this invention is to provide an in-situ testing device and method for simulating boiling fouling on the surface of reactor core cladding tubes, in order to solve the problem of corrosion product deposition testing under supercooled boiling conditions.

[0007] To achieve the above objectives, in one aspect, the present invention provides an in-situ testing device for boiling fouling on the surface of a tube simulating a reactor core flow channel. The device includes a test section pipe, both ends of which are sealed. Several arrayed tubular samples are inserted inside the test section pipe. Each tubular sample contains an internal heating rod. The tubular samples pass through the seals at both ends of the test section pipe and are connected to a pressure regulating device at one end. The pressure regulating device includes a pressure-holding airbag and a high-pressure air pump. Six connecting holes are evenly distributed along the axial direction on one side of the test section pipe. Each connecting hole connects to a medium inlet pipe, a medium outlet pipe, and multiple sealing plugs, respectively. Each sealing plug includes at least one visible sealing plug, and a laser signal transceiver is provided outside the visible sealing plug. The visible sealing plug has a viewing window that allows laser signals emitted by a laser transceiver to pass through and be reflected back by a tubular sample. The laser transceiver is connected to a data processing system. The connecting holes, from top to bottom, connect to a medium outlet pipe, a medium inlet pipe (first type), a visible sealing plug, an open-hole sealing plug, a fully sealed plug, and a second medium inlet pipe. High-flow-rate circulating water flows through the second medium inlet pipe and the medium outlet pipe to simulate core water circulation. Low-flow-rate, high-temperature, high-pressure water flows through the first medium inlet pipe to simulate lateral turbulence. A positioning grid is connected to the inner hole of the open-hole sealing plug. This positioning grid cooperates with the tubular samples arranged in an array within the test section pipe to simulate the influence of the positioning grid on fouling behavior within the core.

[0008] Optionally, the medium outlet pipe, medium inlet pipe one, and medium inlet pipe two are all wrapped with an insulation layer and are all connected to thermocouples extending into each pipe.

[0009] Optionally, the light-transmitting window in the center of the visible sealing plug is a diamond window.

[0010] Optionally, the tubular sample is connected to tubular sample sealing plugs at both ends, with one end of the tubular sample sealing plug having an opening and being connected to the pressure regulating device.

[0011] Optionally, a 4×4 array of tubular samples is inserted inside the test section of the pipe.

[0012] On the other hand, the present invention provides an in-situ testing method for boiling fouling on the surface of a tube simulating a reactor core flow channel. This method uses the in-situ testing device for boiling fouling on the surface of a tube simulating a reactor core flow channel as described in any of the preceding claims. The method includes the following steps:

[0013] The test section pipeline was constructed, tubular samples were inserted, and internal heating rods were installed in each tubular sample. The position of the positioning grid and the number and type of sealing plugs in the test section pipeline were determined according to the experimental requirements to simulate specific working conditions.

[0014] Connect the medium inlet pipe and the medium outlet pipe, and set the temperature and pressure of the medium through a high-temperature and high-pressure water system;

[0015] Install the visual sealing plug and laser signal transceiver to complete the preparation for in-situ measurement;

[0016] The same pressure as that inside the test section is injected into the tubular sample using a pressure-holding airbag and a high-pressure air pump.

[0017] Start measuring and acquiring the operating data of the laser signal transceiver;

[0018] The growth thickness and deposition rate of the deposited layer were analyzed using a data processing system, and the boiling fouling phenomenon on the surface of the tubular sample was evaluated accordingly.

[0019] The present invention discloses the following technical effects:

[0020] This invention presents a testing apparatus and method for simulating boiling fouling on the surface of reactor core cladding tubes, providing an efficient and accurate testing solution for the problem of corrosion product deposition in nuclear reactor core cladding tubes. The apparatus can simulate real reactor core operating conditions, including positioning grids, lateral turbulence, and flow-induced vibration, to obtain test results that more closely resemble reality. Its multi-component replaceable design enhances the flexibility and adaptability of the testing, enabling it to meet various experimental requirements.

[0021] The device employs a laser transceiver and a diamond window to achieve in-situ online measurement of the thickness of scale growth on the surface of tubular samples, ensuring the real-time nature and accuracy of the data. Furthermore, the combination of a pressure-holding airbag and a high-pressure air pump effectively prevents sample creep deformation under high temperature and high pressure conditions, further ensuring the reliability of the measurement results. By analyzing the growth thickness and deposition rate of the deposited layer through the data processing system, the boiling scale phenomenon can be accurately assessed, providing a scientific basis for subsequent research and applications.

[0022] Compared to existing technologies, this invention offers significant advantages in terms of the realism, flexibility, and reliability of simulated operating conditions. It can be used for long-term fixed single tests or rapidly adjusted to adapt to different experimental purposes. These technical effects not only enhance the testing capability for the deposition behavior of corrosion products in the cladding tubes of nuclear reactor cores but also contribute to improving the operational safety of nuclear reactors, predicting the service life of the cladding, and providing important technical support for the safe utilization and sustainable development of nuclear energy. Attached Figure Description

[0023] To more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the drawings used in the embodiments will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0024] Figure 1 This is a front view of the in-situ testing device for boiling fouling on the surface of the tube in the simulated reactor core flow channel according to the present invention.

[0025] In the diagram: 11. Test section pipeline; 12. Seal 1; 13. Seal 2; 14. Tubular sample; 15. Internal heating rod; 16. Tubular sample sealing plug; 21. Medium outlet pipeline; 22. Medium inlet pipeline 1; 23. Visible sealing plug; 24. Opening sealing plug; 25. Fully sealed plug; 26. Medium inlet pipeline 2; 31. Positioning grid; 32. Thermocouple; 33. Insulation layer; 41. Laser signal transceiver; 42. Data processing system; 43. High-pressure air pump; 44. Pressure-holding airbag. Detailed Implementation

[0026] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0027] Fuel cladding tubes in nuclear reactor cores face fouling and corrosion problems during long-term operation, leading to decreased thermal conductivity and reduced local reactivity, thus affecting safe operation. Existing fouling testing methods include orifice accelerated deposition, electromagnetic heating deposition, and internal heating deposition, but each has its limitations: the orifice method ignores the nucleation and boiling mechanism, the electromagnetic method is not suitable for zirconium alloys and is subject to electromagnetic interference, and the internal heating method cannot simulate complex core flow conditions and cannot observe the deposition process in situ.

[0028] To address these issues, this invention proposes a device and method for measuring corrosion product deposition in tubular samples that can simulate the complex flow channel environment of a reactor core. This allows for flexible reproduction of conditions such as positioning grids, flow-induced vibrations, and lateral turbulence in fuel assemblies. Simultaneously, by combining a diamond window, laser ranging technology, and a pressure-holding gasbag / high-pressure pump design, in-situ online measurement of the deposition rate is achieved, thereby accurately obtaining the corrosion product deposition rate of the fuel cladding tube. Based on this technology, more accurate data support will be provided for the safe operation of nuclear reactors and the prediction of cladding tube lifetime, thus making a significant contribution to the safe utilization and sustainable development of nuclear energy.

[0029] To make the above-mentioned objects, features and advantages of the present invention more apparent and understandable, the present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.

[0030] Reference Figure 1 As shown, this embodiment of the invention provides an in-situ testing device for simulating boiling fouling on the surface of a reactor core flow channel. The device includes a test section pipe 11, which is a hollow structure made of high-temperature and high-pressure resistant metal material. The upper and lower ends are sealed with metal seals and connected by flanges. The upper end of the test section pipe 11 has a first seal 12, and the lower end has a second seal 13. Several arrayed tubular samples 14 are inserted inside the test section pipe 11, with appropriate spacing between each sample to simulate the flow characteristics in the reactor core flow channel. Each pipe has an internal heating rod 15 for internal heating. The heating power is precisely adjusted to place the outer surface of the tubular sample 14 under conditions of supercooled nucleus boiling, thereby simulating the boiling fouling phenomenon in the reactor core flow channel.

[0031] The test section pipe 11 has several circular connection holes on one side, which can be flexibly connected to various replaceable components according to experimental requirements. In this embodiment, it includes, from top to bottom, a medium outlet pipe 21, a medium inlet pipe one 22, a visible sealing plug 23, an open sealing plug 24, a fully sealed plug 25, and a medium inlet pipe two 26 connected to each connection hole.

[0032] The fully sealed plug 25 is used to seal any unused openings, ensuring the airtightness of the test section pipe 11. The inner hole of the open-ended sealing plug 24 can be used to connect the positioning grid 31, which is fixed by a threaded connecting rod. The positioning grid 31 cooperates with the arrayed tubular samples 14 to simulate the positioning frame in the reactor core, so as to simulate the effect of the positioning frame in the reactor core on fouling behavior.

[0033] The visible sealing plug 23 can withstand high temperature and pressure and provides an online observation window. Specifically, a diamond window is connected to the middle of the diamond window sealing plug. This diamond window provides a channel for laser light to pass through, allowing the laser transceiver 41 to face the tubular sample 14 within the window. The laser transceiver 41 continuously transmits and receives laser signals and records the interval between each pulse. The signal is transmitted to the data processing system 42, which filters out the reflected signal from the window to obtain the distance between the sample surface and the transceiver. The change in this distance during the experiment represents the growth thickness of the deposited layer, and the rate of change is the deposition rate.

[0034] By installing a diamond viewing window on the test section pipe 11 and aligning it with the laser signal transceiver 41, the thickness and deposition rate of scale growth on the surface of the tubular sample 14 are monitored. One end of the cladding tube has a sealing plug with a connection port, which connects to an internal pressure balancing system consisting of a pressure-holding airbag 44 and a high-pressure air pump 43. This structure effectively prevents sample creep deformation caused by external high-temperature and high-pressure environments, thus avoiding interference with laser ranging results.

[0035] The two medium inlet pipes and the medium outlet pipe 21 are wrapped with heat insulation layers and thermocouples 32 are inserted to ensure that the medium temperature at the inlet and outlet of the test section pipe 11 is constant and measurable.

[0036] It should be understood that multiple media inlet and outlet pipes can be connected simultaneously to simulate lateral turbulence and flow-induced vibration within the reactor core. In this embodiment, two media inlet pipes are configured: media inlet pipe one 22 and media inlet pipe two 26.

[0037] The medium inlet pipe and medium outlet pipe 21 are connected to a high-temperature, high-pressure water system, through which high-temperature water at 310°C and 13.8 MPa is introduced. This high-temperature water contains a specified concentration of dissolved corrosion products. The pipes are wrapped with an insulation layer 33, optionally made of asbestos insulation material, to ensure temperature stability of the medium during transmission. Thermocouples 32 are inserted inside the pipes for real-time monitoring of the inlet and outlet temperatures. Different flow rates can be set in the medium pipes according to experimental requirements. Specifically, a large flow rate of circulating water is introduced into the second medium inlet pipe 26 and the medium outlet pipe 21 to simulate core water circulation; a small flow rate of high-temperature, high-pressure water is introduced into the first medium inlet pipe 22 to simulate lateral turbulence.

[0038] By controlling the temperature and pressure of the medium inlet and outlet pipes and the heating power of the internal heating rod 15, the overall temperature and flow rate of the test section pipe 11 and the boiling conditions on the surface of the tubular sample 14 can be controlled. By adjusting the connection between the positioning grid 31 and different sealing plugs, the influence of the positioning grid 31 on the fouling behavior can be tested. By adjusting the number, position and flow rate of the medium inlet pipe and the medium outlet pipe 21, the influence of lateral turbulence and flow-induced vibration on the fouling behavior can be investigated.

[0039] The tubular sample 14 is connected to tubular sample sealing plugs 16 at both ends. One end of the tubular sample sealing plug 16 has an opening that connects to and is connected to the pressure-holding airbag 44, and then to the high-pressure air pump 43. The tubular sample 14 is filled with internal pressure equal to that of the test section pipe 11, thereby avoiding the change in pipe diameter caused by the creep effect of the high temperature and high pressure environment outside the tubular sample 14, which would interfere with the laser ranging results.

[0040] In one specific embodiment, a 4×4 array of tubular samples 14 is inserted inside the test section pipe 11. Appropriate spacing is maintained between the tubular samples 14 to simulate the flow characteristics in the reactor core channel. Internal heating rods 15 controlled by a DC power supply are inserted inside the tubular samples 14 for internal heating. The heating power is precisely adjusted to place the outer surface of the tubular samples 14 under conditions of supercooled nucleus boiling, thereby simulating the boiling fouling phenomenon in the reactor core channel.

[0041] In one specific embodiment, six threaded connection holes are equidistantly opened on the side of the test section pipe 11, which are connected from top to bottom to the medium outlet pipe 21, the medium inlet pipe 1 22, the visible sealing plug 23, the open sealing plug 24, the fully sealed plug 25, and the medium inlet pipe 26, respectively. Pressure is applied to the sealing gasket by rotating the external pressure nut to ensure tight sealing under high temperature and high pressure.

[0042] In one specific embodiment, the connection hole design on the sidewall of the test section pipe 11 allows for flexible replacement of various components (such as the positioning grid 31, different types of sealing plugs, and media pipes), enabling the device to adapt to various experimental needs. This covers simulation tests of complex operating conditions such as the core positioning grid 31, lateral turbulence, and flow-induced vibration, providing powerful experimental equipment for the study of fouling behavior. Compared to existing technologies, this testing device and method have the advantages of realistic simulation conditions, high flexibility, and reliable connection. It can be used for long-term fixed single-test operations and can also be quickly assembled and adjusted according to the experimental objectives.

[0043] This invention achieves real-time, non-contact measurement of the scale growth thickness and deposition rate on the surface of a tubular sample 14 by combining a laser signal transceiver 41 and a diamond-coated visible sealing plug 23. Compared to traditional offline measurement methods, this device can dynamically reflect the entire process of scale accumulation, providing more accurate experimental data. Currently, the accuracy of laser ranging is at the micrometer level, while the scale thickness in the reactor core cladding tube can reach tens of micrometers, and the effects of high-temperature creep are also on the order of magnitude. The cooperation between the pressure-holding airbag 44 and the high-pressure air pump 43 effectively prevents creep deformation of the tubular sample 14 under high temperature and high pressure, avoids creep interference with the measurement, and ensures the accuracy of the test results.

[0044] This invention also provides an in-situ testing method for boiling fouling on the surface of a simulated reactor core flow channel. This method uses the in-situ testing device for boiling fouling on the surface of a simulated reactor core flow channel described in the above embodiments, and specifically includes the following steps:

[0045] The test section pipeline 11 is constructed, tubular samples 14 are inserted, and an internal heating rod 15 is installed in each tubular sample 14. The position of the positioning grid 31 and the number and type of sealing plugs in the test section pipeline 11 are determined according to the experimental requirements to simulate specific working conditions.

[0046] Connect the medium inlet pipe and the medium outlet pipe 21, and set the temperature and pressure of the medium through a high-temperature and high-pressure water system;

[0047] Install the visual sealing plug 23 and the laser signal transceiver 41 to complete the preparation for in-situ measurement;

[0048] The pressure is injected into the tubular sample 14 by the pressure-holding airbag 44 and the high-pressure air pump 43, with the same pressure as the inside of the test section.

[0049] Start measuring and acquire the operating data of the laser signal transceiver 41;

[0050] The growth thickness and deposition rate of the deposited layer are analyzed by the data processing system 42, and the boiling fouling phenomenon on the surface of the tubular sample 14 is evaluated accordingly.

[0051] The above-described embodiments disclose an in-situ testing apparatus and method for simulating boiling fouling on the surface of reactor core cladding tubes. These methods aim to solve the problem of corrosion product deposition testing in nuclear reactor core cladding tubes under supercooled boiling conditions. Compared with existing technologies, the apparatus of this invention discloses at least the following beneficial effects:

[0052] 1. Simulate real working conditions: By simulating the complex environment of the reactor core flow channel, including the positioning grid 31, lateral turbulence, flow-induced vibration, etc., the working conditions in the actual reactor core can be simulated more realistically.

[0053] 2. Improved testing flexibility: The device design allows for flexible replacement of various components, such as positioning grid 31, different types of sealing plugs, and media pipelines, to adapt to various experimental needs.

[0054] 3. Achieve in-situ online measurement: By combining a diamond window and a laser signal transceiver 41, real-time, non-contact measurement of the scale layer growth thickness and deposition rate on the surface of the tubular sample 14 can be achieved.

[0055] 4. Improve data accuracy: Laser ranging technology can dynamically reflect the entire process of dirt accumulation and provide more accurate experimental data.

[0056] 5. Reduce the impact of high temperature creep: The combination of the pressure-holding airbag 44 and the high-pressure air pump 43 effectively prevents the high temperature and high pressure environment from causing creep deformation of the tubular sample 14, and avoids creep interference with the measurement.

[0057] 6. Evaluation of boiling fouling phenomenon: The growth thickness and deposition rate of the deposited layer are analyzed by the data processing system 42 to evaluate the boiling fouling phenomenon on the surface of the tubular sample 14.

[0058] 7. Optimize the design of existing devices: Compared with existing technologies, the present invention has the advantages of simulating real working conditions, being highly flexible, and having reliable connections. It can be used for long-term fixed single tests, and can also be quickly assembled and adjusted according to the purpose of the test.

[0059] 8. Improve nuclear reactor operation safety: Accurate simulation and testing of corrosion product deposition behavior on the cladding tube surface helps improve reactor operation safety and predict cladding service life.

[0060] All aspects not detailed in this invention are conventional technical means well known to those skilled in the art.

[0061] In the description of this invention, it should be understood that the terms "longitudinal", "lateral", "up", "down", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", etc., indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings, and are only for the convenience of describing this invention, and are not intended to indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation of this invention.

[0062] The embodiments described above are merely preferred embodiments of the present invention and are not intended to limit the scope of the present invention. Various modifications and improvements made by those skilled in the art to the technical solutions of the present invention without departing from the spirit of the present invention should fall within the protection scope defined by the claims of the present invention.

Claims

1. An in-situ testing device for boiling fouling on the surface of a tube simulating a reactor core flow channel, characterized in that, The test section pipe (11) is sealed at both ends and contains several arrayed tubular samples (14). Each tubular sample (14) has an internal heating rod (15) inside. The tubular sample (14) passes through the seals at both ends of the test section pipe (11) and is connected to a pressure regulating device at one end. The pressure regulating device includes a pressure-holding airbag (44) and a high-pressure air pump (43). Six connecting holes are evenly distributed along the axial direction on one side of the test section pipe (11). Each connecting hole is connected to a medium inlet pipe, a medium outlet pipe (21), and multiple sealing plugs. Each sealing plug includes at least one visible sealing plug (23). A laser signal transceiver (41) is provided outside the visible sealing plug (23). The window on the visible sealing plug (23) allows the laser signal transceiver (41) to emit laser signals. Light passes through and is reflected back by the tubular sample (14). The laser signal transceiver (41) is connected to the data processing system (42). Each connection hole is connected from top to bottom to the medium outlet pipe (21), medium inlet pipe one (22), visible sealing plug (23), open sealing plug (24), fully sealed plug (25), and medium inlet pipe two (26). The medium inlet pipe two (26) and the medium outlet pipe (21) are filled with high-flow circulating water to simulate core water circulation. The medium inlet pipe one (22) is filled with low-flow high-temperature and high-pressure water to simulate transverse turbulence. The inner hole of the open sealing plug (24) is connected to a positioning grid (31). The positioning grid (31) cooperates with each tubular sample (14) arranged in the array in the test section pipe (11) to simulate the effect of the positioning frame in the core on the fouling behavior.

2. The in-situ testing device for boiling fouling on the surface of a simulated reactor core flow channel according to claim 1, characterized in that, The medium outlet pipe (21), medium inlet pipe one (22), and medium inlet pipe two (26) are all wrapped with a heat insulation layer (33) and are all connected to thermocouples (32) that extend into each pipe.

3. The in-situ testing device for boiling fouling on the surface of a simulated reactor core flow channel according to claim 1, characterized in that, The light-transmitting window in the middle of the visible sealing plug (23) is a diamond window.

4. The in-situ testing device for boiling fouling on the surface of a simulated reactor core flow channel according to claim 1, characterized in that, The tubular sample (14) is connected to tubular sample sealing plugs (16) at both ends, and one end of the tubular sample sealing plug (16) has an opening and is connected to the pressure regulating device.

5. The in-situ testing device for boiling fouling on the surface of a simulated reactor core flow channel according to claim 1, characterized in that, The test section pipe (11) contains a 4×4 array of tubular samples (14).

6. A method for in-situ testing of boiling fouling on the surface of a simulated reactor core flow channel, using the in-situ testing device for boiling fouling on the surface of a simulated reactor core flow channel as described in any one of claims 1 to 5, characterized in that, Includes the following steps: The test section pipeline (11) is constructed, tubular samples (14) are inserted, and internal heating rods (15) are installed in each tubular sample (14). The position of the positioning grid (31) and the number and type of sealing plugs in the test section pipeline (11) are determined according to the experimental requirements to simulate specific working conditions. Connect the medium inlet pipe and the medium outlet pipe (21), and set the temperature and pressure of the medium through a high temperature and high pressure water system; Install the visual sealing plug (23) and laser signal transceiver (41) to complete the preparation for in-situ measurement; The pressure inside the tubular sample (14) is injected into the test section using a pressure-holding airbag (44) and a high-pressure air pump (43); Start the measurement and acquire the operating data of the laser signal transceiver (41); The growth thickness and deposition rate of the deposited layer were analyzed by the data processing system (42), and the boiling fouling phenomenon on the surface of the tubular sample (14) was evaluated accordingly.

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