High temperature reactor pressure vessel displacement measurement apparatus and support system monitoring apparatus, method

Abstract

The displacement measuring device of the high-temperature reactor pressure vessel is arranged on the chamber wall corresponding to the pressure vessel, and comprises a fixed plate, a displacement sensor, a pulley assembly, a lead wire and a weight block. The displacement sensor and the pulley assembly are fixed to the fixed plate. The first end of the lead wire is used for being fixed to a preset displacement measuring point of the pressure vessel, and the second end of the lead wire is fixedly connected with the weight block through the pulley assembly. The measuring end of the displacement sensor is connected with the lead wire and is used for measuring the displacement change amount of the pressure vessel at the preset displacement measuring point. The displacement measuring device can guarantee the reliability of the displacement sensor beyond the allowable use temperature limit value, and solves the displacement measuring technical problem of the high-temperature reactor primary loop pressure vessel under the thermal state working condition.

Description

Technical Field

[0001] This disclosure pertains to the field of high-temperature gas-cooled reactor displacement measurement technology, specifically relating to a high-temperature reactor pressure vessel displacement measurement device and a support system monitoring device and method. Background Technology

[0002] The primary circuit pressure vessel of a pebble bed modular high-temperature gas-cooled reactor (hereinafter referred to as "HTR") is larger and heavier than that of a pressurized water reactor (PWR). Therefore, the structural form of the pressure vessel support system used in HTR differs significantly from that of the PWR pressure vessel. The HTR pressure vessel support system differs from the PWR pressure vessel support structure in terms of seismic design and load-bearing capacity, representing a first-time application in this project. To ensure the reliability of the unit's operation, the effectiveness of the pressure vessel support system needs to be tested under various operating conditions. This is achieved by comprehensively evaluating parameters such as spatial displacement, tilt, and expansion of the pressure vessel under different operating conditions.

[0003] The HTR design ensures that the reactor pressure vessel centerline is a dead line under any operating condition, meaning that only longitudinal and lateral expansion of the reactor pressure vessel is allowed, and tilting or spatial misalignment of the vessel is not permitted. The steam generator pressure vessel design requires that under any operating condition, the steam generator pressure vessel centerline is only allowed to move horizontally along the direction of the hot gas duct, and tilting or spatial misalignment of the vessel is not permitted.

[0004] Unlike pressurized water reactor (PWR) nuclear power plants, which cover the primary loop pressure vessel with insulation material, HTR reactors do not have insulation material on the surfaces of their pressure vessel shell, steam generator shell, and hot gas duct shell. To ensure that the primary loop compartment concrete does not exceed the 70°C operating temperature limit during normal unit operation, HTRs cover the inner surface of the primary loop compartment with insulation material, and embed cooling water pipes within the concrete to reduce concrete temperature. During normal unit operation, the primary loop compartment is affected by the heat generated by the pressure vessel, with localized ambient temperatures reaching 230–250°C. The compartment is a closed space with all doors closed.

[0005] According to the investigation, the operating temperature of different types of displacement sensors does not exceed 150℃. Even after high-temperature modification, the stable operating temperature of displacement sensors does not exceed 210℃. They cannot be used directly in temperature environments of 230-250℃, which limits the displacement measurement of primary pressure vessels and makes it impossible to carry out the work of verifying the effectiveness of pressure vessel support systems under various working conditions.

[0006] Since the HTR primary circuit pressure vessel chamber is a closed environment, it is impossible to input a cold source into the chamber to actively cool the sensor. Furthermore, due to the limited installation space of the chamber, special methods must be adopted to ensure that the displacement sensor operates stably in environments exceeding its permissible operating temperature.

[0007] At present, there are no experienced engineering precedents, either domestically or internationally, for reference.

[0008] To address the aforementioned issues, it is necessary to propose a reasonably designed and effective displacement measurement device and support system monitoring device and method for high-temperature reactor pressure vessels. Summary of the Invention

[0009] The present disclosure aims to at least solve one of the technical problems existing in the prior art, and to provide a high-temperature reactor pressure vessel displacement measuring device and a support system monitoring device and method.

[0010] One aspect of this disclosure provides a displacement measuring device for a high-temperature reactor pressure vessel, applied to a pebble bed modular high-temperature gas-cooled reactor. The pressure vessel is disposed in a primary circuit compartment, the primary circuit compartment is provided with a compartment wall, and the displacement measuring device is disposed in the compartment wall corresponding to the pressure vessel. The displacement measuring device includes a fixed plate, a displacement sensor, a pulley assembly, a lead wire, and a weight block.

[0011] The displacement sensor and the pulley assembly are fixed to the fixing plate;

[0012] The first end of the lead wire is used to fix it to a preset displacement measurement point of the pressure vessel, and the second end of the lead wire passes through the pulley assembly and is fixedly connected to the weight block.

[0013] The measuring end of the displacement sensor is connected to the lead wire and is used to measure the displacement change of the lead wire at the preset displacement measuring point, thereby measuring the displacement change of the pressure vessel at the preset displacement measuring point.

[0014] Optionally, the displacement sensor is fixed to the fixing plate along its length.

[0015] Optionally, the measuring device further includes a heat insulation cover, which is disposed over the displacement sensor.

[0016] Optionally, an insulation layer is provided on the inner side of the compartment wall, the insulation layer is provided with a groove, and the displacement measuring device is provided in the groove.

[0017] Another aspect of this disclosure provides a monitoring device for a high-temperature reactor pressure vessel support system, including a primary loop compartment, a pressure vessel disposed within the primary loop compartment, a processor, and the plurality of displacement measuring devices described above; wherein...

[0018] Multiple displacement measuring devices are respectively installed on the chamber wall corresponding to the preset displacement measuring points of the pressure vessel;

[0019] The processor is electrically connected to multiple displacement measuring devices, and is used to calculate the displacement of the pressure vessel based on the displacement signals received from the multiple displacement measuring devices, and to determine the working state of the pressure vessel support system based on the displacement of the pressure vessel.

[0020] Optionally, the pressure vessel includes a reactor pressure vessel, a steam generator, and hot gas ducts connecting the reactor pressure vessel and the steam generator respectively;

[0021] The plurality of displacement measuring devices include:

[0022] The first displacement measuring device is installed on the top wall of the compartment wall and corresponds to the top of the reactor pressure vessel;

[0023] The second displacement measuring device is installed on the bottom wall of the compartment wall and corresponds to the bottom of the reactor pressure vessel;

[0024] The third displacement measuring device is installed on the side wall of the compartment wall and corresponds to the circumferential direction of the reactor pressure vessel;

[0025] A fourth displacement measuring device is installed on the top wall of the chamber wall and corresponds to the top of the steam generator shell;

[0026] The fifth displacement measuring device is installed on the bottom wall of the chamber wall and corresponds to the bottom of the steam generator shell;

[0027] The sixth displacement measuring device is installed on the side wall of the chamber wall and corresponds circumferentially to the steam generator shell in the direction perpendicular to the hot gas duct.

[0028] The seventh displacement measuring device is installed on the side wall of the chamber wall and corresponds circumferentially to the radial center line of the steam generator shell and the axial center line of the hot gas duct.

[0029] The eighth displacement measuring device is installed on the side wall of the compartment wall corresponding to the lower part of the reactor pressure vessel, and corresponds to the circumferential direction parallel to the hot gas duct and collinear with the radial center line of the reactor pressure vessel.

[0030] The ninth displacement measuring device is installed on the side wall of the compartment wall corresponding to the upper part of the reactor pressure vessel, and corresponds to the circumferential direction parallel to the hot gas duct and collinear with the radial center line of the reactor pressure vessel.

[0031] The tenth displacement measuring device is installed on the side wall of the compartment wall corresponding to the upper part of the steam generator shell, and corresponds to the circumferential direction parallel to the hot gas duct and collinear with the radial center line of the steam generator shell;

[0032] The eleventh displacement measuring device is installed on the side wall of the compartment wall corresponding to the lower part of the steam generator shell, and corresponds to the circumferential direction parallel to the hot gas duct and collinear with the radial center line of the steam generator shell.

[0033] Another aspect of this disclosure provides a monitoring method for a high-temperature reactor pressure vessel support system, wherein the pressure vessel includes a reactor pressure vessel, a steam generator, and hot gas ducts respectively connecting the reactor pressure vessel and the steam generator, and the method includes:

[0034] The expansion and deformation of the reactor pressure vessel, the expansion and deformation of the steam generator shell, the horizontal displacement of the steam generator shell, the axial tilt of the reactor pressure vessel, and the axial tilt of the steam generator are obtained respectively.

[0035] Determine whether any one of the following exceeds its preset displacement threshold: the expansion deformation of the reactor pressure vessel, the expansion deformation of the steam generator shell, the horizontal displacement of the steam generator shell, the axial tilt of the reactor pressure vessel, and the axial tilt of the steam generator shell. If it does, then the pressure vessel support system is deemed abnormal.

[0036] Optionally, the expansion deformation of the reactor pressure vessel includes axial expansion and radial expansion, and obtaining the expansion deformation of the reactor pressure vessel includes:

[0037] The first axial displacement and the second axial displacement of the top and bottom of the reactor pressure vessel are obtained respectively;

[0038] The axial expansion of the reactor pressure vessel is obtained by calculating the sum of the first axial displacement and the second axial displacement.

[0039] The radial displacement of the reactor pressure vessel is directly obtained to obtain the radial expansion of the reactor pressure vessel.

[0040] Optionally, the expansion deformation of the steam generator shell includes axial expansion and radial expansion, and obtaining the expansion deformation of the steam generator shell includes:

[0041] The third axial displacement and the fourth axial displacement of the top and bottom of the steam generator casing are obtained respectively;

[0042] The axial expansion of the steam generator casing is obtained by calculating the sum of the third axial displacement and the fourth axial displacement.

[0043] The radial displacement of the steam generator housing perpendicular to the direction of the hot gas duct is directly obtained to obtain the radial expansion of the steam generator housing.

[0044] Optionally, obtaining the horizontal displacement of the steam generator casing includes:

[0045] Obtain the horizontal displacement change at the sidewall of the steam generator housing opposite to the hot gas duct, where the radial centerline of the steam generator housing is collinear with the axial centerline of the hot gas duct;

[0046] The horizontal displacement of the steam generator shell is obtained by subtracting the radial expansion of the steam generator shell from the horizontal displacement change.

[0047] Optionally, obtaining the axial tilt of the reactor pressure vessel includes:

[0048] The first horizontal displacement and the second horizontal displacement of the upper and lower parts of the reactor pressure vessel along the direction of the hot gas duct are obtained respectively.

[0049] Determine whether the difference between the first horizontal displacement and the second horizontal displacement is zero. If it is zero, the tilt of the reactor pressure vessel axis is zero. If it is not zero, calculate the tilt of the reactor pressure vessel axis based on the first horizontal displacement and the second horizontal displacement.

[0050] Optionally, obtaining the axial tilt of the steam generator casing includes:

[0051] The third and fourth horizontal displacements of the upper and lower parts of the steam generator housing along the direction of the hot gas duct are obtained respectively.

[0052] Determine whether the difference between the third horizontal displacement and the fourth horizontal displacement is zero. If it is zero, the tilt of the steam generator shell axis is zero. If it is not zero, calculate the tilt of the reactor pressure vessel axis based on the third horizontal displacement and the fourth horizontal displacement.

[0053] This disclosed example of a displacement measuring device for a high-temperature reactor pressure vessel indirectly transfers the heat generated by the displacement measuring device to the cooling water pipes within the chamber wall, thus reducing the temperature of the displacement measuring device. Simultaneously, placing the displacement measuring device on the chamber wall keeps it away from heat sources such as the pressure vessel, further reducing the temperature at which the displacement measuring device is heated. This allows a displacement sensor with a 210°C temperature limit to perform remote measurements in environments approaching 250°C, ensuring the reliability of the displacement sensor even when its permissible operating temperature limit is exceeded. This solves the technical challenge of displacement measurement in the primary loop pressure vessel of a high-temperature reactor under hot operating conditions.

[0054] The high-temperature reactor pressure vessel support system monitoring device of this disclosure has multiple displacement measuring devices installed on the chamber wall corresponding to the preset displacement measuring points of the pressure vessel. This ensures that the displacement measuring devices can measure the displacement of the pressure vessel even when the temperature exceeds its allowable operating temperature limit. The processor determines the working state of the pressure vessel support system based on the displacement of the pressure vessel, thereby enabling the verification of the effectiveness of the pressure vessel support system under various operating conditions.

[0055] The monitoring method for the pressure vessel support system of the high-temperature reactor disclosed herein solves the problem of temperature limitation in displacement measurement of the primary loop pressure vessel of the pebble bed modular high-temperature gas-cooled reactor. By measuring the displacement of the pressure vessel, the effectiveness of the pressure vessel support system under various operating conditions can be monitored, and this method has been verified in the hot functional test phase of the dual-reactor primary loop system of the pebble bed modular high-temperature gas-cooled reactor. Attached Figure Description

[0056] Figure 1 This is a schematic diagram of the structure of a high-temperature reactor pressure vessel displacement measuring device according to one embodiment of the present disclosure;

[0057] Figure 2 This is a schematic diagram of the structure of a monitoring device for a high-temperature reactor pressure vessel support system according to another embodiment of this disclosure;

[0058] Figure 3 This is a schematic diagram showing the distribution of preset displacement measurement points in a high-temperature reactor pressure vessel according to another embodiment of this disclosure;

[0059] Figure 4 This is a schematic diagram showing the distribution of the third preset displacement measuring points and the installation position of the third displacement measuring device in another embodiment of this disclosure.

[0060] Figure 5 This is a flowchart illustrating a monitoring method for a high-temperature reactor pressure vessel support system in another embodiment of this disclosure. Detailed Implementation

[0061] To enable those skilled in the art to better understand the technical solutions of the embodiments of this disclosure, the embodiments of this disclosure will be further described in detail below with reference to the accompanying drawings and specific implementation methods.

[0062] like Figure 1 and Figure 2 As shown, one aspect of this disclosure provides a high-temperature reactor pressure vessel displacement measuring device 100, applied to a pebble bed modular high-temperature gas-cooled reactor. The pressure vessel 210 is disposed within a primary loop compartment 220, which has a compartment wall 230. Cooling water pipes 240 are installed within the compartment wall 230. The displacement measuring device 100 is disposed within the compartment wall 230 corresponding to the pressure vessel 210. The displacement measuring device 100 includes a fixing plate 110, a displacement sensor 120, a pulley assembly 130, a lead wire 140, and a weight block 150. This displacement measuring device fully utilizes the design of the cooling water pipes 240 within the compartment wall 230 to indirectly transfer the heat from the displacement sensor 120 to the cooling water pipes 240.

[0063] The displacement sensor 120 and the pulley assembly 130 are fixed to the fixed plate 110.

[0064] It should be noted that in this embodiment, the fixing plate 110 can be a metal fixing plate. Specifically, the metal fixing plate is welded to the annular steel strip of the cabin wall 230. The fixing plate 110 is used to fix the displacement sensor 120 and its matching pulley assembly 130, and to provide a heat conduction path for the displacement sensor 120.

[0065] The first end of the lead wire 140 is used to fix it to a preset displacement measurement point of the pressure vessel 210, and the second end of the lead wire 140 passes through the pulley assembly 130 and is fixedly connected to the weight block 150.

[0066] It should be noted that in this embodiment, a high-temperature magnet 250 is adsorbed at a preset displacement measurement point of the pressure vessel 210, and the first end of the lead wire 140 is fixed at the preset displacement measurement point by the high-temperature magnet 250.

[0067] It should be noted that the weight block 150 can be a hammer, meaning that the second end of the lead wire 140 is suspended from the hammer to ensure that the lead wire 140 maintains a certain tension. The second end of the lead wire 140 passes through the pulley assembly 130 to convert the displacement sensor 120 into a vertical arrangement, which can further move the displacement sensor 120 away from the heat source.

[0068] like Figure 1The pulley assembly 130 includes a fixing member 131 and a pulley 132, with the pulley 132 fixed to the fixing plate 110 by the fixing member 131. The number and structure of the pulleys 132 are not specifically limited in this embodiment; for example, there may be one pulley 132 or multiple pulleys 132, or a single pulley or a double pulley system, which can be selected according to actual needs.

[0069] like Figure 1 As shown, the measuring end of the displacement sensor 120 is connected to the lead wire 140 to measure the displacement change of the lead wire 140 at a preset displacement measurement point, thereby measuring the displacement change of the pressure vessel 210 at the preset displacement measurement point. In other words, the displacement change of the pressure vessel 210 at the preset displacement measurement point is indirectly obtained by measuring the displacement change of the lead wire 140 at the preset displacement measurement point using the displacement sensor 120. This eliminates the need to place the displacement sensor 120 directly on the surface of the pressure vessel 210 for displacement measurement, ensuring the reliability of the displacement sensor 120 even when its allowable operating temperature limit is exceeded.

[0070] It should be noted that, in this embodiment, the displacement sensor 120 can measure the horizontal and vertical displacement of the pressure vessel 210 at a preset displacement measurement point. That is, in this embodiment, the displacement measuring device 100 can be installed on the chamber wall 230 parallel to the preset displacement measurement point of the pressure vessel 210, thus measuring the horizontal displacement of the preset displacement measurement point. Alternatively, the displacement measuring device 100 can be installed on the chamber wall 230 perpendicular to the preset displacement measurement point of the pressure vessel 210, thus measuring the vertical displacement of the preset displacement measurement point.

[0071] This disclosed example of a displacement measuring device for a high-temperature reactor pressure vessel indirectly transfers the heat generated by the displacement measuring device to the cooling water pipes within the chamber wall, thus reducing the temperature of the displacement measuring device. Simultaneously, placing the displacement measuring device on the chamber wall keeps it away from heat sources such as the pressure vessel, further reducing the temperature at which the displacement measuring device is heated. This allows a displacement sensor with a 210°C temperature limit to perform remote measurements in environments approaching 250°C, ensuring the reliability of the displacement sensor even when its permissible operating temperature limit is exceeded. This solves the technical challenge of displacement measurement in the primary loop pressure vessel of a high-temperature reactor under hot operating conditions.

[0072] For example, such as Figure 1 and Figure 2 As shown, an insulation layer 260 is provided on the inner side of the compartment wall 230, and a groove 261 is provided in the insulation layer 260. A displacement measuring device 100 is provided in the groove 261.

[0073] Specifically, such as Figure 1As shown, at the location where the displacement measuring device 100 needs to be installed on the chamber wall 230, the insulation layer 260 is removed to form a groove 261 exposing the chamber wall 230. The displacement measuring device 100 is then installed in the groove 261. This further keeps the displacement measuring device 100 away from heat sources such as pressure vessels and brings it closer to the cooling water pipe 240, thereby further reducing the temperature of the displacement measuring device 100 and ensuring its reliability.

[0074] For example, such as Figure 1 As shown, the displacement sensor 120 is fixed to the fixing plate 110 along its length. That is, the displacement sensor 120 is parallel to the cabin wall 230 along its length, and also parallel to the cooling water pipe 240 along its length.

[0075] In the above embodiments, the displacement sensor 120 is fixed to the fixing plate 110 along its length direction. On the one hand, by changing the arrangement of the displacement sensor 120, it can be moved away from the heat source, reducing the heating of the displacement sensor 120. On the other hand, the length direction of the displacement sensor 120 is parallel to the cooling water pipe 240, which can maximize the transfer of the heat generated by the displacement sensor 120 to the cooling water pipe 240.

[0076] For example, such as Figure 1 As shown, the high-temperature reactor pressure vessel displacement measuring device 100 also includes a heat insulation cover 160, which covers the displacement sensor 120.

[0077] Specifically, such as Figure 1 As shown, the heat insulation cover 160 is fixed on the heat insulation layer 260, and the displacement sensor 120, the fixing plate 110 and the pulley assembly 130 are all covered inside.

[0078] In the above embodiments, the heat insulation cover 160 can be used to reduce the convective heat transfer efficiency between the hot airflow in the primary loop chamber and the displacement sensor 120, thereby reducing the temperature of the displacement sensor 120 and increasing the reliability of the displacement sensor 120.

[0079] like Figure 2 As shown, another aspect of this disclosure provides a monitoring device 200 for a high-temperature reactor pressure vessel support system, including a primary loop compartment 220, a pressure vessel 210 disposed within the primary loop compartment 220, a processor (not shown in the figure), and a plurality of displacement measuring devices 100 as described above. The specific structure of the displacement measuring devices 100 has been described in detail above and will not be repeated here.

[0080] like Figure 2As shown, multiple displacement measuring devices 100 are respectively installed on the chamber wall 230 corresponding to the preset displacement measuring points of the pressure vessel 210.

[0081] The processor is electrically connected to multiple displacement measuring devices 100 to calculate the displacement of the pressure vessel 210 based on the displacement signals received from the multiple displacement measuring devices, and to determine the working state of the pressure vessel support system based on the displacement of the pressure vessel 210.

[0082] Specifically, the processor compares the displacement of the pressure vessel 210 measured by multiple displacement measuring devices 100 with a preset displacement. If the measured displacement of the pressure vessel 210 exceeds the preset displacement, the processor can determine that the working state of the pressure vessel support system is abnormal and adjustment of the support system is required. If the measured displacement of the pressure vessel 210 is within the range of the preset displacement, the processor can determine that the working state of the pressure vessel support system is normal and no adjustment is required.

[0083] It should be noted that in this embodiment, the processor can be a PLC, MCU, or CPU, and can be selected according to actual needs. This embodiment does not make any specific limitations.

[0084] For example, such as Figure 3 As shown, the pressure vessel 210 includes a reactor pressure vessel 211, a steam generator 212, and hot gas ducts 213 that connect the reactor pressure vessel 211 and the steam generator 212 respectively.

[0085] The plurality of displacement measuring devices specifically include:

[0086] The first displacement measuring device (not shown in the figure) is installed on the top wall of the compartment wall 230 and corresponds to the top of the reactor pressure vessel 211.

[0087] like Figure 3 As shown, specifically in this embodiment, a first preset displacement measuring point B is provided on the top of the reactor pressure vessel 211. Specifically, the first preset displacement measuring point B is located on the top cover of the reactor pressure vessel 211. That is, the first displacement measuring device is located on the top wall of the compartment wall 230 directly above the first preset displacement measuring point B, and can be used to measure the axial expansion of the top of the reactor pressure vessel 211.

[0088] The second displacement measuring device (not shown in the figure) is located at the bottom of the compartment wall 230 and corresponds to the bottom of the reactor pressure vessel 211.

[0089] like Figure 3As shown, specifically in this embodiment, a second preset displacement measuring point C is provided at the bottom of the reactor pressure vessel 211. Specifically, the second preset displacement measuring point C is located at the lower flange of the discharge nozzle. That is, the second displacement measuring device is located on the bottom wall of the compartment wall 230 directly below the second preset displacement measuring point C, and can be used to measure the axial expansion of the bottom of the reactor pressure vessel 211.

[0090] The third displacement measuring device (not shown in the figure) is installed on the side wall of the compartment wall 230 and corresponds to the circumferential direction of the reactor pressure vessel 211.

[0091] like Figure 3 As shown, specifically, in this embodiment, multiple third preset displacement measurement points A are arranged circumferentially at the hot gas duct 213 corresponding to the reactor pressure vessel 211.

[0092] like Figure 3 and Figure 4 As shown, in this embodiment, multiple third preset displacement measurement points A are set at the lower part of the reactor pressure vessel 211, and four are arranged circumferentially along the hot gas duct 213 corresponding to the reactor pressure vessel 211. Two of the third preset displacement measurement points A are parallel to the direction of the hot gas duct 213 and collinear with the radial centerline of the reactor pressure vessel 211. The other two third preset displacement measurement points A are perpendicular to the hot gas duct 213 and collinear with the radial centerline of the reactor pressure vessel 211. Correspondingly, four third displacement measuring devices are also provided, distributed on the compartment wall 230 corresponding to each third preset displacement measurement point A, which can be used to measure the radial expansion of the reactor pressure vessel 211. Simultaneously, the third displacement measuring devices can also be used to measure the horizontal displacement of the lower part of the reactor pressure vessel 211.

[0093] It should be noted that the location of the third preset displacement measurement point A is not specifically limited. It can be located on the upper or lower part of the reactor pressure vessel 211, as long as it is set on the side wall of the reactor pressure vessel 211.

[0094] A fourth displacement measuring device (not shown in the figure) is installed on the top of the compartment wall 230 and corresponds to the top of the steam generator 212.

[0095] like Figure 3 As shown, specifically in this embodiment, a fourth preset displacement measuring point E is provided on the top of the steam generator 212 housing. Specifically, the fourth preset displacement measuring point E is located on the top cover of the blower housing. That is, the fourth displacement measuring device is located on the top wall of the compartment wall 230 directly above the fourth preset displacement measuring point E, and can be used to measure the axial expansion of the top of the steam generator 212 housing.

[0096] The fifth displacement measuring device (not shown in the figure) is located at the bottom of the chamber wall 230 and corresponds to the bottom of the steam generator 212 shell.

[0097] like Figure 3 As shown, specifically in this embodiment, a fifth preset displacement measuring point F is provided at the bottom of the steam generator 212 shell. Specifically, the fifth preset displacement measuring point F is located at the main water supply nozzle of the bottom end cap of the steam generator shell. That is, the fifth displacement measuring device is located on the bottom wall of the compartment wall 230 directly below the fifth preset displacement measuring point F, and can be used to measure the axial expansion of the bottom of the steam generator 212 shell.

[0098] The sixth displacement measuring device (not shown in the figure) is installed on the side wall of the chamber wall 230 and corresponds circumferentially to the steam generator 212 shell in the direction perpendicular to the hot gas duct 213.

[0099] like Figure 3 As shown, specifically in this embodiment, a sixth preset displacement measuring point G is circumferentially arranged on the steam generator 212 shell in the direction perpendicular to the hot gas duct 213. Specifically, the sixth preset displacement measuring point G is located on the side wall of the steam generator shell in the direction perpendicular to the hot gas duct 213. That is, the sixth displacement measuring device is located on the side of the compartment wall 230 corresponding to the sixth preset displacement measuring point G, and can be used to measure the radial expansion of the steam generator 212 shell along the direction perpendicular to the hot gas duct 213.

[0100] The seventh displacement measuring device (not shown in the figure) is installed on the side wall of the compartment wall 230 and corresponds circumferentially to the radial center line of the steam generator 212 shell and the axial center line of the hot gas duct 213.

[0101] like Figure 3 As shown, specifically, in this embodiment, a seventh preset displacement measuring point D is provided on the side wall of the steam generator 212 housing where the radial centerline of the steam generator 212 housing is collinear with the axial centerline of the hot gas duct 213. Specifically, the seventh preset displacement measuring point D is located at the support lug of the steam generator housing. That is, the seventh displacement measuring device is located on the side of the compartment wall 230 corresponding to the seventh preset displacement measuring point, and can be used to measure the horizontal change of the steam generator 212 housing on the side wall away from the hot gas duct 213, where the radial centerline of the steam generator 212 housing is collinear with the axial centerline of the hot gas duct 213.

[0102] Of course, the seventh preset displacement measurement point D can also be set on the side wall of the steam generator 212 housing facing the hot gas duct 213, and the radial center line of the steam generator 212 housing and the axial center line of the hot gas duct 213 are collinear. It can be selected according to actual needs, and this embodiment does not make specific limitations.

[0103] The eighth displacement measuring device (not shown in the figure) is installed on the side wall of the compartment wall 230 corresponding to the lower part of the reactor pressure vessel 212, and corresponds to the circumferential direction parallel to the hot gas duct 213 and collinear with the radial center line of the reactor pressure vessel 212.

[0104] like Figure 3 As shown, an eighth preset displacement measuring point is provided on the lower part of the sidewall of the reactor pressure vessel 212. In this embodiment, the eighth preset displacement measuring point coincides with the third preset displacement measuring point A mentioned above. According to the above description, multiple third preset displacement measuring points A are provided on the lower part of the reactor pressure vessel 212, two of which are parallel to the direction of the hot gas duct 213 and collinear with the radial centerline of the reactor pressure vessel 211. Correspondingly, the eighth displacement measuring device corresponds to the two aforementioned third preset displacement measuring points A on the lower part of the reactor pressure vessel 212. That is, as... Figure 3 As shown, the eighth displacement measuring device can be installed on the side wall of the left compartment wall 230 corresponding to the third preset displacement measuring point A, or on the side wall of the right compartment wall 230 corresponding to the third preset displacement measuring point A. The eighth displacement measuring device can be used to measure the horizontal displacement of the lower part of the reactor pressure vessel 212.

[0105] The ninth displacement measuring device (not shown in the figure) is installed on the side wall of the compartment wall 230 corresponding to the upper part of the reactor pressure vessel 212, and corresponds to the circumferential direction parallel to the hot gas duct 213 and collinear with the radial center line of the reactor pressure vessel 212.

[0106] like Figure 3 As shown, specifically in this embodiment, a ninth preset displacement measuring point is provided on the top of the reactor pressure vessel 212, which coincides with the first preset displacement measuring point B. Corresponding to the first preset displacement measuring point B, parallel to the direction of the hot gas duct 213, and collinear with the radial centerline of the reactor pressure vessel 212, two eighth displacement measuring devices are arranged opposite each other on the side wall of the compartment wall 230. The eighth displacement measuring devices can be set at... Figure 3 The side wall of the left-side compartment wall 230 can also be set at... Figure 3 On the right-side compartment wall 230, the ninth displacement measuring device can be used to measure the horizontal displacement of the top of the reactor pressure vessel 212.

[0107] It should be noted that the ninth preset displacement measurement point can also be set on the side wall of the upper part of the reactor pressure vessel 212. This embodiment does not make specific limitations and can be selected according to actual needs.

[0108] The tenth displacement measuring device (not shown in the figure) is installed on the side wall of the compartment wall 230 corresponding to the upper part of the steam generator 212 shell, and corresponds to the circumferential direction parallel to the hot gas duct 213 and collinear with the radial center line of the steam generator 212 shell.

[0109] Specifically, such as Figure 3 As shown, a tenth preset displacement measuring point is provided on the top of the steam generator 212 shell, which coincides with the fourth displacement measuring point E described above. Corresponding to the direction of the fourth preset displacement measuring point E, which is parallel to the hot gas duct 213 and collinear with the radial center line of the steam generator 212 shell, two tenth displacement measuring devices are arranged opposite each other on the side wall of the compartment wall 230. The tenth displacement measuring devices can be used to measure the horizontal displacement of the top of the steam generator 212 shell.

[0110] It should be noted that the tenth preset displacement measurement point can also be set on the side wall of the upper part of the steam generator 212 shell. This embodiment does not make specific limitations and can be selected according to actual needs.

[0111] The eleventh displacement measuring device (not shown in the figure) is installed on the side wall of the compartment wall 230 corresponding to the lower part of the steam generator 212 shell, and corresponds to the circumferential direction parallel to the hot gas duct 213 and collinear with the radial center line of the steam generator 212 shell.

[0112] Specifically, such as Figure 3 As shown, an eleventh preset displacement measuring point (not shown in the figure) is set on the lower side wall of the steam generator 212, parallel to the direction of the hot gas duct 213 and collinear with the radial center line of the steam generator 212 shell. Corresponding to the eleventh preset displacement measuring point, two eleventh displacement measuring devices are set opposite each other on the side wall of the compartment wall 230, parallel to the direction of the hot gas duct 213 and collinear with the radial center line of the steam generator 212 shell. The eleventh displacement measuring device can be used to measure the horizontal displacement of the lower part of the steam generator 212 shell. The eleventh displacement measuring device can be set at... Figure 3 The left-side compartment wall 230 shown can also be installed in Figure 3 The right-hand side of the cabin wall 230 is shown.

[0113] In the above embodiments, by setting multiple preset displacement measurement points on the reactor pressure vessel 211 and steam generator 212 shells, and setting multiple displacement measurement devices on the compartment walls 230 corresponding to the multiple preset displacement measurement points, the axial and radial displacements of the reactor pressure vessel 211 and steam generator 212 shells are measured by using horizontal and axial measurement methods, and then the expansion deformation, horizontal displacement, and axial tilt of the primary loop pressure vessel 210 are calculated.

[0114] The high-temperature reactor pressure vessel support system monitoring device of this disclosure has multiple displacement measuring devices installed on the chamber wall corresponding to the preset displacement measuring points of the pressure vessel. This ensures that the displacement measuring devices can measure the displacement of the pressure vessel even when the temperature exceeds its allowable operating temperature limit. The processor determines the working state of the pressure vessel support system based on the displacement of the pressure vessel, thereby enabling the verification of the effectiveness of the pressure vessel support system under various operating conditions.

[0115] like Figure 5 As shown, another aspect of this disclosure provides a monitoring method S200 for a high-temperature reactor pressure vessel support system. The pressure vessel 210 includes a reactor pressure vessel 211, a steam generator 212, and hot gas ducts 213 connecting the reactor pressure vessel 211 and the steam generator 212 respectively. The method S200 includes:

[0116] S210. Obtain the expansion deformation of the reactor pressure vessel, the expansion deformation of the steam generator shell, the horizontal displacement of the steam generator shell, the axial tilt of the reactor pressure vessel, and the axial tilt of the steam generator, respectively.

[0117] For example, the expansion and deformation of the reactor pressure vessel includes axial expansion and radial expansion, and obtaining the expansion and deformation of the reactor pressure vessel includes:

[0118] The first axial displacement of the top of the reactor pressure vessel 211 is measured by the first displacement measuring device. That is, the first axial displacement is the difference in distance between the top of the reactor pressure vessel 211 and the top wall of the compartment wall 230 in the initial state and the target state.

[0119] The second axial displacement of the bottom of the reactor pressure vessel 211 is measured by the second displacement measuring device. That is, the second axial displacement is the difference in distance between the bottom of the reactor pressure vessel 211 and the bottom wall of the compartment wall 230 in the initial state and the target state.

[0120] The sum of the first axial displacement and the second axial displacement is the axial expansion of the reactor pressure vessel 211.

[0121] The radial displacement of the reactor pressure vessel 211 is directly measured using a third displacement measuring device. In other words, the radial displacement of the reactor pressure vessel 211 is the difference in distance between the circumference of the reactor pressure vessel 211 and the side wall of the compartment wall 230 in the initial and target states. The radial displacement of the reactor pressure vessel 211 is also the radial expansion of the reactor pressure vessel.

[0122] For example, the expansion deformation of the steam generator housing includes axial expansion and radial expansion, and obtaining the expansion deformation of the steam generator housing includes:

[0123] The third axial displacement of the top of the steam generator 212 shell is measured by the fourth displacement measuring device. That is, the third axial displacement is the difference in distance between the top of the steam generator 212 shell and the top wall of the compartment wall 230 in the initial state and the target state.

[0124] The fourth axial displacement of the bottom of the steam generator 212 shell is directly measured by the fifth displacement measuring device. That is, the fourth axial displacement is the difference in distance between the bottom of the steam generator 212 shell and the bottom wall of the compartment wall 230 in the initial state and the target state.

[0125] The sum of the third and fourth axial displacements is the axial expansion of the steam generator 212 shell.

[0126] The radial displacement of the steam generator 212 shell perpendicular to the hot gas duct 213 is directly measured by the sixth displacement measuring device, thus obtaining the radial expansion of the steam generator 212 shell. In other words, the radial displacement of the steam generator 212 shell is the difference in distance between the circumferential direction of the steam generator 212 shell perpendicular to the hot gas duct 213 and the side wall of the compartment wall 230 in the initial and target states. The radial displacement of the steam generator 212 shell is also the radial expansion of the steam generator 212 shell.

[0127] For example, obtaining the horizontal displacement of the steam generator housing includes:

[0128] The horizontal displacement change at the sidewall of the steam generator shell 212 that is opposite to the hot gas duct 213 is measured by the seventh displacement measuring device.

[0129] In other words, the change in horizontal displacement of the steam generator 212 shell is the difference in distance between the side wall of the steam generator shell 212 away from the hot gas duct 213 and the side wall of the compartment wall 230 at the point where the radial center line of the steam generator 212 shell is collinear with the axial center line of the hot gas duct 213.

[0130] The horizontal displacement of the steam generator shell is obtained by subtracting the radial expansion of the steam generator shell from the horizontal displacement change.

[0131] Of course, besides the method in this embodiment, another method can be used to obtain the horizontal displacement of the steam generator shell. The first horizontal displacement change can be measured using a displacement measuring device at the location where the radial centerline of the steam generator shell 212 faces the hot gas duct 213 and is collinear with the axial centerline of the hot gas duct 213. The first horizontal displacement change is the distance difference between the sidewall of the steam generator shell 212 facing the hot gas duct 213 and the sidewall of the compartment wall 230 at the location where the radial centerline of the steam generator shell 212 and the axial centerline of the hot gas duct 213 are collinear in the initial and target states.

[0132] By adding the first horizontal displacement change to the radial expansion of the steam generator 212 shell, the horizontal displacement of the steam generator shell can be obtained.

[0133] For example, obtaining the axial tilt of the reactor pressure vessel includes:

[0134] The first horizontal displacement of the lower part of reactor pressure vessel 212 along the direction of hot gas duct 213 is measured by the eighth displacement measuring device. The second horizontal displacement of the upper part of reactor pressure vessel 211 is measured by the ninth displacement measuring device.

[0135] Determine if the difference between the first and second horizontal displacements is zero. If it is zero, the tilt of the reactor pressure vessel 211 axis is zero, meaning the reactor pressure vessel 211 has not tilted. If it is not zero, calculate the tilt of the reactor pressure vessel axis based on the first and second horizontal displacements.

[0136] Specifically, by drawing the geometric figure, inputting the first horizontal displacement, the second horizontal displacement, the radius of the reactor pressure vessel 212 cylinder, and the vertical height, the tilt angle of the reactor pressure vessel 212 along the horizontal direction can be calculated based on the geometric relationship.

[0137] For example, obtaining the axial tilt of the steam generator housing includes:

[0138] The third horizontal displacement of the upper part of the steam generator 212 shell along the direction of the hot gas duct 213 is measured using the tenth displacement measuring device. The fourth horizontal displacement of the lower part of the steam generator 212 shell along the direction of the hot gas duct 213 is measured using the eleventh displacement measuring device.

[0139] Determine if the difference between the third and fourth horizontal displacements is zero. If it is zero, the tilt of the steam generator 212 shell axis is zero, meaning the steam generator 212 shell is not tilted. If it is not zero, calculate the tilt of the steam generator 212 shell axis based on the third and fourth horizontal displacements.

[0140] Specifically, by drawing the geometric figure and inputting the third horizontal displacement, the fourth horizontal displacement, the radius of the shell of the steam generator 212, and the vertical height, the tilt angle of the shell of the steam generator 212 along the horizontal direction can be calculated through geometric relationships.

[0141] S220. Determine whether any one of the following exceeds its preset displacement threshold: the expansion deformation of the reactor pressure vessel, the expansion deformation of the steam generator shell, the horizontal displacement of the steam generator shell, the axial tilt of the reactor pressure vessel, and the axial tilt of the steam generator shell. If it exceeds the threshold, determine that the pressure vessel support system is abnormal.

[0142] Specifically, the processor compares the expansion and deformation of the reactor pressure vessel 211, the expansion and deformation of the steam generator 212 shell, the horizontal displacement of the steam generator 212 shell, the axial tilt of the reactor pressure vessel 211, and the axial tilt of the steam generator 212 shell with their corresponding preset displacement thresholds. If any one of them exceeds its preset displacement threshold, the pressure vessel support system is deemed abnormal and requires adjustment. If all the above displacements are within the preset displacement thresholds, the pressure vessel support system is deemed normal.

[0143] The monitoring method for the pressure vessel support system of the high-temperature reactor disclosed herein solves the problem of temperature limitation in displacement measurement of the primary loop pressure vessel of the pebble bed modular high-temperature gas-cooled reactor. By measuring the displacement of the pressure vessel, the effectiveness of the pressure vessel support system under various operating conditions can be monitored, and this method has been verified in the hot functional test phase of the dual-reactor primary loop system of the pebble bed modular high-temperature gas-cooled reactor.

[0144] It is understood that the above embodiments are merely exemplary implementations used to illustrate the principles of the embodiments of this disclosure, and the embodiments of this disclosure are not limited thereto. For those skilled in the art, various modifications and improvements can be made without departing from the spirit and essence of the embodiments of this disclosure, and these modifications and improvements are also considered to be within the protection scope of the embodiments of this disclosure.

Claims

1. A monitoring device for a high-temperature reactor pressure vessel support system, characterized in that, It includes a primary loop compartment, a pressure vessel disposed within the primary loop compartment, a processor, and multiple high-temperature reactor pressure vessel displacement measuring devices; wherein, Multiple displacement measuring devices for the high-temperature reactor pressure vessel are respectively installed on the chamber wall corresponding to preset displacement measuring points of the pressure vessel; wherein, The high-temperature reactor pressure vessel displacement measuring device is applied to a pebble bed modular high-temperature gas-cooled reactor. The pressure vessel is located in the primary circuit compartment, which has a compartment wall. The high-temperature reactor pressure vessel displacement measuring device is located on the compartment wall corresponding to the pressure vessel, so as to indirectly transfer the heat generated by the displacement measuring device to the cooling water pipes inside the compartment wall, thereby reducing the temperature of the displacement measuring device. The high-temperature reactor pressure vessel displacement measuring device includes a fixed plate, a displacement sensor, a pulley assembly, a lead wire, and a weight block. The displacement sensor and the pulley assembly are fixed to the fixing plate, wherein the fixing plate is used to fix to the annular steel strip of the compartment wall; The first end of the lead wire is used to fix it to a preset displacement measurement point of the pressure vessel, and the second end of the lead wire passes through the pulley assembly and is fixedly connected to the weight block. The measuring end of the displacement sensor is connected to the lead wire to measure the displacement change of the lead wire at the preset displacement measuring point, thereby indirectly measuring the displacement change of the pressure vessel at the preset displacement measuring point, so as to ensure the reliability of the displacement sensor when it exceeds its allowable operating temperature limit. The processor is electrically connected to multiple displacement measuring devices, and is used to calculate the displacement of the pressure vessel based on the displacement signals received from the multiple displacement measuring devices, and to determine the working state of the pressure vessel support system based on the displacement of the pressure vessel. The pressure vessel includes a reactor pressure vessel, a steam generator, and hot gas ducts that connect the reactor pressure vessel and the steam generator respectively. The plurality of high-temperature reactor pressure vessel displacement measuring devices include: The first displacement measuring device is installed on the top wall of the compartment wall and corresponds to the top of the reactor pressure vessel; The second displacement measuring device is installed on the bottom wall of the compartment wall and corresponds to the bottom of the reactor pressure vessel; The third displacement measuring device is installed on the side wall of the compartment wall and corresponds to the circumferential direction of the reactor pressure vessel; A fourth displacement measuring device is installed on the top wall of the chamber wall and corresponds to the top of the steam generator shell; The fifth displacement measuring device is installed on the bottom wall of the chamber wall and corresponds to the bottom of the steam generator shell; The sixth displacement measuring device is installed on the side wall of the chamber wall and corresponds circumferentially to the steam generator shell in the direction perpendicular to the hot gas duct. The seventh displacement measuring device is installed on the side wall of the chamber wall and corresponds circumferentially to the radial center line of the steam generator shell and the axial center line of the hot gas duct. The eighth displacement measuring device is installed on the side wall of the compartment wall corresponding to the lower part of the reactor pressure vessel, and corresponds to the circumferential direction parallel to the hot gas duct and collinear with the radial centerline of the reactor pressure vessel. The ninth displacement measuring device is installed on the side wall of the compartment wall corresponding to the upper part of the reactor pressure vessel, and corresponds to the circumferential direction parallel to the hot gas duct and collinear with the radial center line of the reactor pressure vessel. The tenth displacement measuring device is installed on the side wall of the compartment wall corresponding to the upper part of the steam generator shell, and corresponds to the circumferential direction parallel to the hot gas duct and collinear with the radial center line of the steam generator shell; The eleventh displacement measuring device is installed on the side wall of the compartment wall corresponding to the lower part of the steam generator shell, and corresponds to the circumferential direction parallel to the hot gas duct and collinear with the radial center line of the steam generator shell.

2. The apparatus according to claim 1, characterized in that, The displacement sensor is fixed to the fixing plate along its length.

3. The apparatus according to claim 2, characterized in that, The measuring device also includes a heat insulation cover, which is placed over the displacement sensor.

4. The apparatus according to any one of claims 1 to 3, characterized in that, The inner side of the cabin wall is provided with an insulation layer, and the insulation layer is provided with grooves, in which the displacement measuring device is installed.

5. A monitoring method for a high-temperature reactor pressure vessel support system, wherein the pressure vessel includes a reactor pressure vessel, a steam generator, and hot gas ducts respectively connecting the reactor pressure vessel and the steam generator, characterized in that, The method using the monitoring device for the high-temperature reactor pressure vessel support system according to any one of claims 1 to 4 includes: The expansion and deformation of the reactor pressure vessel, the expansion and deformation of the steam generator shell, the horizontal displacement of the steam generator shell, the axial tilt of the reactor pressure vessel, and the axial tilt of the steam generator are obtained respectively. Determine whether any one of the following exceeds its preset displacement threshold: the expansion deformation of the reactor pressure vessel, the expansion deformation of the steam generator shell, the horizontal displacement of the steam generator shell, the axial tilt of the reactor pressure vessel, and the axial tilt of the steam generator shell. If it does, then the pressure vessel support system is deemed abnormal.

6. The monitoring method according to claim 5, characterized in that, The expansion and deformation of the reactor pressure vessel includes axial expansion and radial expansion. Obtaining the expansion and deformation of the reactor pressure vessel includes: The first axial displacement and the second axial displacement of the top and bottom of the reactor pressure vessel are obtained respectively; The axial expansion of the reactor pressure vessel is obtained by calculating the sum of the first axial displacement and the second axial displacement. The radial displacement of the reactor pressure vessel is directly obtained to obtain the radial expansion of the reactor pressure vessel.

7. The monitoring method according to claim 5, characterized in that, The expansion deformation of the steam generator shell includes axial expansion and radial expansion. Obtaining the expansion deformation of the steam generator shell includes: The third and fourth axial displacements of the top and bottom of the steam generator casing are obtained respectively. The axial expansion of the steam generator casing is obtained by calculating the sum of the third axial displacement and the fourth axial displacement. The radial displacement of the steam generator housing perpendicular to the direction of the hot gas duct is directly obtained to obtain the radial expansion of the steam generator housing.

8. The monitoring method according to claim 7, characterized in that, The step of obtaining the horizontal displacement of the steam generator casing includes: Obtain the horizontal displacement change at the sidewall of the steam generator housing opposite to the hot gas duct, where the radial centerline of the steam generator housing is collinear with the axial centerline of the hot gas duct; The horizontal displacement of the steam generator shell is obtained by subtracting the radial expansion of the steam generator shell from the horizontal displacement change.

9. The monitoring method according to any one of claims 5 to 8, characterized in that, The step of obtaining the axial tilt of the reactor pressure vessel includes: The first horizontal displacement and the second horizontal displacement of the upper and lower parts of the reactor pressure vessel along the direction of the hot gas duct are obtained respectively. Determine whether the difference between the first horizontal displacement and the second horizontal displacement is zero. If it is zero, the tilt of the reactor pressure vessel axis is zero. If it is not zero, calculate the tilt of the reactor pressure vessel axis based on the first horizontal displacement and the second horizontal displacement.

10. The monitoring method according to any one of claims 5 to 8, characterized in that, The step of obtaining the axial tilt of the steam generator casing includes: The third and fourth horizontal displacements of the upper and lower parts of the steam generator housing along the direction of the hot gas duct are obtained respectively. Determine whether the difference between the third horizontal displacement and the fourth horizontal displacement is zero. If it is zero, the tilt of the steam generator housing axis is zero. If it is not zero, calculate the tilt of the steam generator housing axis based on the third horizontal displacement and the fourth horizontal displacement.

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