Containment leakage simulation system and method for nuclear power plants

Abstract

This application relates to a nuclear power plant containment leakage simulation system and method. The method employs the aforementioned nuclear power plant containment leakage simulation system to simulate the sensor signals of leaks. A leak of a certain diameter can be selected, and leakage tests can be conducted on various containment structures to collect data. Simulated leakage detection of the same leak in different containment structures can be performed. This allows the nuclear power plant containment leakage simulation system to collect sensor data from leak tests under various operating conditions. Furthermore, by comparing and analyzing sensor data from known operating conditions with sensor data from unknown operating conditions, parameters such as the inner diameter and location of the leak in the unknown operating condition can be determined.

Description

Technical Field

[0001] This application relates to the field of nuclear power plant technology, and in particular to a nuclear power plant containment leakage simulation system and method. Background Technology

[0002] The nuclear power plant containment vessel, as the outermost of the three barriers of a nuclear reactor, is used to prevent radioactive materials from spreading from the reactor to the outside in the event of an accident, thus fulfilling its function as a safety protection barrier. However, with the increase in service life, the steel lining structure of the containment vessel is prone to problems such as debonding from the reinforced concrete, weld cracking, and aging of the seals of penetrations, leading to containment vessel leakage and causing serious safety accidents.

[0003] Currently, leak detection in containment structures generally employs two methods: the pressure change method and the bubble method. The pressure change method involves pressurizing the containment structure and observing pressure changes over a period of time to determine if a leak has occurred. However, this method is time-consuming and cannot pinpoint the leak location. The bubble method involves spraying soapy water onto the area to be tested and observing the formation of bubbles to determine if a leak has occurred. However, this method has low detection efficiency and requires cleaning; otherwise, the soapy water will affect the lifespan of the containment structure.

[0004] Acoustic leak detection is a newly proposed leak detection method in recent years. It has advantages such as being pollution-free, having high detection efficiency, and being able to locate leak points, and has been widely used in leak detection for oil pipelines and other applications. However, the containment structure is a steel plate bonded to concrete, and the sound wave propagation law is complex. Traditional acoustic leak detection methods cannot locate leaks in complex containment structures. There is an urgent need for a nuclear power plant containment leak simulation system to simulate safety leaks and provide an experimental platform for the research of acoustic leak location methods. This includes channel sensitivity testing, signal attenuation measurement, leak location calibration, background noise testing and identification, etc., which will then guide acoustic leak detection methods to obtain parameters such as leak location. Summary of the Invention

[0005] Therefore, it is necessary to provide a nuclear power plant containment leakage simulation system and method to address the problems that complex containment structure leaks cannot be simulated, thus making it impossible to match corresponding acoustic parameters for leaks under different operating conditions, and consequently, to analyze parameters such as leak location based on the obtained detection data.

[0006] A nuclear power plant containment leakage simulation system, the nuclear power plant containment leakage simulation system comprising:

[0007] The simulated shell includes a column and a dome shell. The column is vertically connected to at least two sidewall shells from top to bottom. The dome shell is connected to the top of the top sidewall shells. The wall thicknesses of the at least two sidewall shells and the shells in the dome shell are different. Each shell has multiple perforations, and the inner diameters of the perforations on a single shell are different. The number and diameter of the perforations on different shells correspond one-to-one.

[0008] A sensor is disposed on the inner surface of the simulated housing, and multiple sensors are arranged around each of the leak holes. The sensors are used to detect the leakage data of the corresponding leak holes.

[0009] A through-connector is provided, which is correspondingly installed in the leakage hole. The through-connector includes a vent valve and a connecting pipe connected together. The connecting pipe passes through the leakage hole to connect the internal space and the external space of the simulation shell. The vent valve is located outside the simulation shell.

[0010] The aforementioned nuclear power plant containment leakage simulation system, during the simulation and detection of containment leaks, utilizes the fact that each outer shell has a different thickness, and that the first, second, and third outer shells form a column, resulting in a similar overall structure. This allows it to simulate the structure of columnar and dome-shaped outer shells of varying thicknesses within a nuclear power plant. Since each outer shell has multiple leak holes with different inner diameters, and the number and size of these leak holes on different outer shells correspond one-to-one, a leak can be simulated by opening the vent valve of any leak hole after pressurization inside the simulated containment. Leakage data can then be collected using sensors around that leak hole. Furthermore, since each enclosure has a different thickness and shape, leakage data from holes of different diameters on any enclosure can be collected and compared. The number and size of multiple holes on different enclosures correspond one-to-one; that is, the holes are divided into multiple groups, each group containing multiple holes of the same diameter but located on different enclosures. Therefore, a hole of a certain diameter can be selected, and leakage tests can be conducted on various enclosures to collect data. Simulated leakage detection of the same hole on different enclosures can be performed. This allows the nuclear power plant containment leakage simulation system to collect sensor data for leakage tests under various operating conditions. Then, by comparing sensor data from known operating conditions with sensor data from unknown operating conditions, the inner diameter and location of the hole under unknown operating conditions can be determined.

[0011] In one embodiment, the nuclear power plant containment leakage simulation system further includes a pressurization connector that penetrates the simulated containment.

[0012] In one embodiment, the nuclear power plant containment leak simulation system further includes gas cylinders;

[0013] The through connector also includes an air inflator valve and a bottle valve, wherein the air inflator valve is connected to the interior of the simulated housing;

[0014] The gas cylinder opening is connected to a first interface and multiple second interfaces, and the multiple second interfaces correspond one-to-one with and are connected to the cylinder valves of the multiple through connectors;

[0015] The pressurization connector includes a pressurization tube, a third interface, and a fourth interface. The pressurization tube passes through the simulation housing, the third interface communicates with the interior of the simulation housing, and the fourth interface is connected to the first interface.

[0016] In one embodiment, the nuclear power plant containment leakage simulation system further includes a pressure detection unit and a safety unit;

[0017] The pressure detection unit includes a detection tube and a pressure gauge connected together. The detection tube passes through the simulation housing, and the pressure gauge is located outside the simulation housing.

[0018] The safety unit includes a safety pipe and a safety valve connected together. The safety pipe passes through the simulation housing, and the safety valve is located outside the simulation housing.

[0019] In one embodiment, the detection tube penetrates the dome housing, and the safety tube penetrates the dome housing.

[0020] In one embodiment, the nuclear power plant containment leakage simulation system further includes an electrical penetration device that passes through the simulated containment, and the sensor cable passes through and is sealed in the electrical penetration device.

[0021] In one embodiment, the simulated outer shell has a container door.

[0022] In one embodiment, the nuclear power plant containment leakage simulation system further includes multiple gas flow meters, each of which corresponds to and is connected to a plurality of vent valves.

[0023] In one embodiment, the simulated shell includes an inner liner and a casting layer, the casting layer surrounding the inner liner, and the casting layer being divided into connecting portions of different thicknesses from top to bottom in a vertical direction. Each connecting portion and the inner liner at a corresponding position form a first outer shell, a second outer shell, and a third outer shell arranged from top to bottom.

[0024] One embodiment of this application also provides a method for simulating leakage in a nuclear power plant containment structure. The method uses the nuclear power plant containment structure leakage simulation system to simulate sensor signals indicating leakage from the leak. The method includes the following steps:

[0025] Close all the aforementioned vent valves and pressurize the interior of the simulated housing;

[0026] When the vent valve corresponding to any of the leak holes is opened, the gas inside the simulated housing leaks outward through the through connector corresponding to the leak hole, and the sensor corresponding to the leak hole collects leakage data during the leakage process.

[0027] Leakage tests were sequentially performed on multiple leak holes of different inner diameters in one of the housings, and leakage data of the corresponding sensors were collected;

[0028] Leakage tests were conducted on each of the leak holes with the same inner diameter in each of the housings, and data from the corresponding sensors were collected.

[0029] After the data collection by the sensor is completed, the pressure inside the simulated housing is released.

[0030] Using the aforementioned nuclear power plant containment leakage simulation method, a nuclear power plant containment leakage simulation system is used to simulate the sensor signals of leaks. A leak of a certain diameter can be selected, and leakage tests can be conducted on various containment structures to collect data. Simulated leakage detection of the same leak in different containment structures can be performed. Thus, the nuclear power plant containment leakage simulation system can collect sensor data from leak tests of leaks under various operating conditions. Furthermore, by comparing and analyzing the sensor data of the leakage process under unknown operating conditions with the sensor data of the known operating conditions, the inner diameter and location of the leak under unknown operating conditions can be determined. Attached Figure Description

[0031] Figure 1 This is a schematic diagram of a nuclear power plant containment leakage simulation system according to one embodiment.

[0032] Figure 2 for Figure 1 Enlarged view of the medium-pressure connection.

[0033] Figure 3 This is a schematic diagram of a sensor arrangement around a leak hole according to one embodiment.

[0034] Explanation of icon numbers:

[0035] 100 - Nuclear Power Plant Containment Leakage Simulation System;

[0036] 110 - Simulated shell; 111 - Dome shell; 112 - First shell; 113 - Second shell; 114 - Third shell; 115 - Leakage hole;

[0037] 120-sensor;

[0038] 130 - Through connector; 131 - Air release valve; 132 - Connecting pipe; 133 - Air inflator; 134 - Bottle valve;

[0039] 140 - Pressurization connector; 141 - Pressurization hose; 142 - Third interface; 143 - Fourth interface;

[0040] 150 - Gas cylinder; 151 - First interface; 152 - Second interface;

[0041] 160-Pressure testing section; 161-Detection tube; 162-Pressure gauge; 163-Safety section; 164-Safety tube; 165-Safety valve;

[0042] 170 - Electrical penetration; 171 - Container door; 172 - Gas flow meter; 173 - Lighting lamp. Detailed Implementation

[0043] To make the above-mentioned objectives, features, and advantages of this application more apparent and understandable, the specific embodiments of this application are described in detail below with reference to the accompanying drawings. Many specific details are set forth in the following description to provide a thorough understanding of this application. However, this application can be implemented in many other ways different from those described herein, and those skilled in the art can make similar modifications without departing from the spirit of this application. Therefore, this application is not limited to the specific embodiments disclosed below.

[0044] In the description of this application, it should be understood that if terms such as "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential" appear, these terms 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 application and simplifying the description, and do not 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 application.

[0045] Furthermore, where the terms "first" and "second" appear, these terms are for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Thus, a feature defined with "first" or "second" may explicitly or implicitly include at least one of that feature. In the description of this application, where the term "multiple" appears, "multiple" means at least two, such as two, three, etc., unless otherwise explicitly specified.

[0046] In this application, unless otherwise expressly specified and limited, the terms "installation," "connection," "joining," and "fixing," etc., should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components, unless otherwise expressly limited. Those skilled in the art can understand the specific meaning of the above terms in this application based on the specific circumstances.

[0047] In this application, unless otherwise expressly specified and limited, the use of descriptions such as "above" or "below" the second feature indicates that the first and second features are in direct contact or indirect contact via an intermediate medium. Furthermore, "above," "on top of," and "over" the second feature can mean that the first feature is directly above or diagonally above the second feature, or simply that the first feature is at a higher horizontal level than the second feature. Similarly, "below," "below," and "under" the second feature can mean that the first feature is directly below or diagonally below the second feature, or simply that the first feature is at a lower horizontal level than the second feature.

[0048] It should be noted that if an element is referred to as being "fixed to" or "set on" another element, it can be directly on the other element or there may be an intervening element. If an element is considered to be "connected to" another element, it can be directly connected to the other element or there may be an intervening element. If so, the terms "vertical," "horizontal," "upper," "lower," "left," "right," and similar expressions used in this application are for illustrative purposes only and do not represent the only possible implementation.

[0049] See Figure 1 and Figure 3, Figure 1 A schematic diagram of the structure of a nuclear power plant containment leakage simulation system 100 according to an embodiment of this application is shown. The nuclear power plant containment leakage simulation system 100 provided in an embodiment of this application includes: a simulation shell 110, a sensor 120, and a through connector 130.

[0050] In the aforementioned nuclear power plant containment leakage simulation system 100, the simulated containment 110 includes a column and a dome-shaped outer shell 111. The column is vertically connected from top to bottom to at least two sidewall shells. The number of sidewall shells can be two, three, or more. In this embodiment, the sidewall shells include a first shell 112, a second shell 113, and a third shell 114. The dome-shaped outer shell 111 is connected to the top of the first shell 112. The dome is either a partially spherical shell or a curved shell and protrudes away from the main body. The wall thickness of each of the first shell 112, second shell 113, third shell 114, and dome-shaped outer shell 111 is different. The term "shell" refers to the first shell 112, second shell 113, third shell 114, and dome-shaped outer shell 111. Each outer shell has multiple leakage holes 115, meaning that the first outer shell, second outer shell, third outer shell, and dome outer shell each have multiple leakage holes. The inner diameters of the multiple leakage holes 115 on a single outer shell are different from each other; for example, the inner diameters of the multiple leakage holes on the first outer shell are different from each other. The number and diameter of the multiple leakage holes 115 on different outer shells correspond one-to-one. Sensors 120 are disposed on the inner surface of the simulated housing 110, and multiple sensors 120 are arranged around each leakage hole 115. The sensors 120 are used to detect leakage data of the corresponding leakage hole 115. Through connectors 130 are correspondingly installed through the leakage holes 115. The through connectors 130 include a vent valve 131 and a connecting pipe 132 connected together. The connecting pipe 132 passes through the leakage hole 115 to connect the internal space and the external space of the simulated housing 110, and the vent valve 131 is located on the outside of the simulated housing 110.

[0051] In the process of simulating and detecting containment leaks, the aforementioned nuclear power plant containment leakage simulation system 100 utilizes the fact that each outer shell has a different thickness, and that the first outer shell 112, the second outer shell 113, and the third outer shell 114 form a column, resulting in a similar overall structure. This allows it to simulate the structure of columns and dome-shaped outer shells 111 of a nuclear power plant with varying thicknesses. Since each outer shell has multiple leakage holes 115, and the inner diameters of these holes on a single outer shell are different, the number and size of the multiple leakage holes 115 on different outer shells correspond one-to-one. Therefore, after pressurizing the interior of the simulated containment 110, the vent valve 131 of any one of the leakage holes 115 can be opened to simulate a leak, and leakage data can be collected through sensors 120 surrounding that leakage hole 115. Meanwhile, since the thickness and shape of each shell are different, leakage data of different diameter holes 115 on the same shell can be collected and compared and analyzed by selecting any shell. At the same time, the number and size of multiple holes 115 on different shells correspond one-to-one, that is, the holes 115 are divided into multiple groups, and the multiple holes 115 in each group have the same diameter but are set on different shells. Therefore, a hole 115 of a certain diameter can be selected to conduct leakage tests on various shells and collect data. Simulated leakage detection of the same hole 115 on different shells can be carried out. Thus, the sensor 120 data of leakage tests of holes 115 under various operating conditions can be collected by the nuclear power plant containment leakage simulation system 100. Then, the sensor 120 data of the known operating conditions can be compared and analyzed with the sensor 120 data of the unknown operating conditions leakage process, so as to know the inner diameter and location of the hole 115 under the unknown operating conditions.

[0052] Specifically, by example, the inner diameters of the multiple holes 115 on a single outer shell are different, and the number and size of the multiple holes 115 on different outer shells correspond one-to-one. That is, the first outer shell, the second outer shell, the third outer shell, and the dome outer shell are each provided with multiple holes of different diameters. The number and diameter of the multiple holes on the first outer shell, the second outer shell, the third outer shell, and the dome outer shell are corresponding. For example, if the first outer shell 112 has holes 115 with diameters of 0.5mm, 1.0mm, and 2.0mm, then correspondingly, the second outer shell 113 has holes 115 with diameters of 0.5mm, 1.0mm, and 2.0mm, the third outer shell 114 has holes 115 with diameters of 0.5mm, 1.0mm, and 2.0mm, and the dome outer shell 111 has holes 115 with diameters of 0.5mm, 1.0mm, and 2.0mm.

[0053] like Figure 3Preferably, multiple sensors 120 are arranged around each leak hole 115. The multiple sensors 120 around each leak hole 115 are divided into multiple groups, and the multiple groups of sensors 120 are evenly arranged around the circumference of the leak hole 115. Each group of sensors 120 is radially arranged along the radial direction of the leak hole 115. Specifically, each group of sensors 120 includes 3-4 sensors 120, and the spacing between each sensor 120 is 300mm.

[0054] In other embodiments, a sensor 120 is arranged around each hole 115, or multiple sensors 120 are arranged around each hole 115 in a circumferential arrangement.

[0055] In one embodiment, the nuclear power plant containment leakage simulation system 100 further includes a pressurization connector 140 that penetrates the simulation housing 110 and is used to pressurize the interior of the simulation housing from the outside of the simulation housing 110 through the pressurization connector 140.

[0056] In one embodiment, the nuclear power plant containment leak simulation system 100 further includes a gas cylinder 150. The through-connector 130 also includes an inflation valve 133 and a cylinder valve 134, with the inflation valve 133 communicating with the interior of the simulated containment 110. The gas cylinder 150 has a first interface 151 and multiple second interfaces 152 connected to its opening, with each of the second interfaces 152 corresponding to and communicating with one of the cylinder valves 134 of the through-connector 130. The pressurization connector 140 includes a pressurization pipe 141, a third interface 142, and a fourth interface 143. The pressurization pipe 141 penetrates the simulated containment 110, the third interface 142 communicates with the interior of the simulated containment 110, and the fourth interface 143 connects to the first interface 151. Because the internal space of the simulated containment 110 is large, the pressurization and depressurization processes take a long time, and personnel cannot enter the interior during simulated leak detection.

[0057] Therefore, through the above design, when it is necessary to conduct a simulated leakage test by pressurizing the interior of the simulated housing 110, the first interface 151, the fourth interface 143, and the second interface 152 are closed, and the third interface 142 is opened to pressurize the interior of the simulated housing 110. The cylinder valve 134 is closed, and the air inflator valve 133 and the air release valve 131 are opened, thereby realizing the simulated leakage test of the internal pressurization of the simulated housing 110. When a rapid test is required, when conducting a simulated test for any leak 115, the air inflator valve 133 and the third interface 142 are closed, and the first interface 151, the fourth interface 143, and the second interface 152 corresponding to the leak 115 are opened. The gas cylinder 150 is pressurized through the pressurization pipe 141 and a certain pressure is maintained. Then, the air release valve 131 corresponding to the leak 115 is opened, thereby realizing the simulated leakage test of the simulated housing 110 through the gas cylinder 150.

[0058] In one embodiment, the nuclear power plant containment leakage simulation system 100 further includes a pressure detection unit 160 and a safety unit 163. The pressure detection unit 160 includes a connected detection pipe 161 and a pressure gauge 162. The detection pipe 161 penetrates the simulated containment 110, and the pressure gauge 162 is located outside the simulated containment 110. The safety unit 163 includes a connected safety pipe 164 and a safety valve 165. The safety pipe 164 penetrates the simulated containment 110, and the safety valve 165 is located outside the simulated containment 110. When the pressure gauge 162 indicates an abnormal internal pressure in the simulated containment 110, the safety valve 165 is opened, and air is released through the safety unit 163 to ensure normal pressure inside the simulated containment 110.

[0059] In one embodiment, the detection tube 161 penetrates the dome housing 111, and the safety tube 164 penetrates the dome housing 111. Since the pressurized gas generally accumulates from the bottom to the top of the simulation housing 110, if the pressure near the dome is too high, it indicates that the pressure inside the simulation housing 110 has reached the pressure relief standard. This avoids the situation where the pressure gauge 162 is abnormally displayed at the bottom, but the pressure near the dome is normal, thus allowing for a better understanding of the pressure limit of the simulation housing 110.

[0060] In one embodiment, the nuclear power plant containment leakage simulation system 100 further includes an electrical penetration 170, which passes through the simulation housing 110. The cable of the sensor 120 passes through the electrical penetration 170 and is sealed to prevent the nuclear power plant containment leakage simulation system 100 from leaking gas.

[0061] In one embodiment, the simulated shell is provided with a container door 171, which allows staff to inspect the inside of the simulated shell 110. At the same time, when conducting a simulated leak test of the simulated shell 110 through the gas cylinder 150, staff can perform relevant inspections and manual monitoring inside the simulated shell 110. If repairs are needed, they can be carried out immediately, thereby improving the efficiency of the test.

[0062] Specifically, the nuclear power plant containment leak simulation system 100 also includes a lighting lamp 173, installed on the dome, for providing illumination to the interior of the simulated containment 110.

[0063] In one embodiment, the nuclear power plant containment leakage simulation system 100 also includes multiple gas flow meters 172, which correspond one-to-one with and are connected to multiple vent valves 131. This allows the gas flow meters 172 to monitor whether the vent valves 131 are closed and whether there is a leak. At the same time, the gas flow rate during the leakage process of the leak hole 115 can also be monitored to assist in the test, such as judging the pressure reduction inside the simulated containment 110 or the gas cylinder 150 by the decrease in gas flow rate.

[0064] In one embodiment, the simulated shell 110 includes an inner liner and a casting layer. The casting layer surrounds the inner liner and is divided into connecting parts of different thicknesses from top to bottom in the vertical direction. Each connecting part and the corresponding inner liner form a first outer shell 112, a second outer shell 113, and a third outer shell 114 arranged from top to bottom. This allows for drilling holes in the inner liner first, then passing the connecting pipe 132 through the holes in the inner liner and welding the connecting pipe 132 to the inner liner. Subsequently, by casting the casting layer outside the inner liner and shaping it into different thicknesses from top to bottom and allowing it to solidify, the first outer shell 112, the second outer shell 113, and the third outer shell 114 are obtained. This facilitates the installation and fixing of the through connector 130, and since the inner liner has the same thickness, it is not necessary to design shells of different shapes and thicknesses solely through the inner liner, thus saving costs.

[0065] Specifically, the inner lining layer is 6mm thick, 150mm in diameter, and 2000mm in height. The inner lining layer is made of carbon steel and has a maximum bearing capacity of 0.6MPa. The cast-in-place layer is a concrete layer.

[0066] In other embodiments, the inner lining may also be made of other materials, such as steel with different carbon contents cast according to the iron-carbon phase diagram, or alloy steel containing other metals. The other metals are selected and proportioned according to the actual pressure required by the simulated shell 110, which will not be elaborated here.

[0067] In other embodiments, the casting layer can also be other materials, such as asphalt, or other mixtures that solidify after casting. The casting mixture can be obtained by innovating and optimizing the casting layer process, parameters and fatigue life based on research in civil engineering, composite materials and other fields. This will not be elaborated further.

[0068] One embodiment of this application also provides a method for simulating leakage in a nuclear power plant containment structure. The method uses a nuclear power plant containment leakage simulation system 100 to simulate the signal from sensor 120 indicating leakage from a leak hole 115. The method includes the following steps:

[0069] Close all vent valves 131, pressurize the interior of the simulated housing 110, and maintain the pressure for a certain period of time. If the pressure drop inside the simulated housing 110 is within a specific range, the sealing performance meets the requirements, and subsequent tests can be conducted. If the pressure drop is greater than the specific range, the sealing performance does not meet the requirements. The non-destructive testing method is used to perform leak detection tests on the nuclear power plant containment leakage simulation system. After the leak is found and repaired, the pressure test is repeated until the sealing performance meets the requirements.

[0070] A set of sensors 120 are installed around each leak hole 115 inside the simulated housing 110, and the sampling rate, sampling time, and leakage alarm value parameters of the sensors 120 are set.

[0071] Open the vent valve 131 corresponding to any of the leak holes 115 to simulate the leakage of gas inside the housing 110 through the through connector 130 corresponding to the leak hole 115. The sensor 120 corresponding to the leak hole 115 collects leakage data during the leakage process.

[0072] Leakage tests are sequentially conducted on multiple holes 115 with different inner diameters in one of the outer shells, and leakage data from the corresponding sensors 120 are collected. This step primarily involves collecting leakage data from sensors corresponding to holes with different inner diameters in one of the first, second, third, and dome shells. This allows for the control of shell variables and the study of leakage conditions at holes with different inner diameters. When a known leak has occurred in an actual operating condition, the inner diameter of the hole in the actual operating condition can be determined by comparing the leak data obtained in this step.

[0073] Leakage tests were conducted on holes 115 with the same inner diameter in each shell, and data from the corresponding sensors 120 were collected. This step primarily involves collecting leakage data from sensors corresponding to holes of a specific inner diameter in each of the first, second, third, and dome shells. This allows for the control of the hole's inner diameter and the study of leakage conditions at the same hole in different shells. When leakage occurs at a hole with a known inner diameter under actual operating conditions, the thickness of the unknown shell containing the hole can be determined by comparing the leak data obtained in this step.

[0074] The above two steps can also be used to conduct leakage tests on all the leak holes with different outer shells and different inner diameters in the simulated housing 110 to obtain a leakage data comparison table of leak holes with different outer shell thicknesses and different inner diameters, thereby guiding the data analysis process monitored by the sensor during actual leakage.

[0075] After the data collection by sensor 120 is completed, the pressure inside the simulation housing 110 is released.

[0076] Using the aforementioned nuclear power plant containment leakage simulation method, the nuclear power plant containment leakage simulation system 100 simulates the sensor 120 signal of leaking through the leak hole 115. A leak hole 115 of a certain diameter can be selected, and leakage tests can be conducted on various outer shells to collect data. Simulated leakage detection of the same leak hole 115 on different outer shells can be performed. Thus, the nuclear power plant containment leakage simulation system 100 can collect sensor 120 data for leakage tests of leak holes 115 under various operating conditions. Furthermore, by comparing and analyzing the sensor 120 data of the leakage process under unknown operating conditions with the sensor 120 data of the known operating conditions, the inner diameter and location of the leak hole 115 under unknown operating conditions can be determined.

[0077] The technical features of the above embodiments can be combined in any way. For the sake of brevity, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0078] The embodiments described above are merely illustrative of several implementation methods of this application, and while the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the patent application. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of this application, and these all fall within the protection scope of this application. Therefore, the protection scope of this patent application should be determined by the appended claims.

Claims

1. A nuclear power plant containment leakage simulation system, characterized in that, The nuclear power plant containment leakage simulation system includes: The simulated shell includes a column and a dome shell. The column is vertically connected to at least two sidewall shells from top to bottom. The dome shell is connected to the top of the top sidewall shells. The wall thicknesses of the at least two sidewall shells and the shells in the dome shell are different. Each shell has multiple perforations, and the inner diameters of the perforations on a single shell are different. The number and diameter of the perforations on different shells correspond one-to-one. A sensor is disposed on the inner surface of the simulated housing, and multiple sensors are arranged around each of the leak holes. The sensors are used to detect the leakage data of the corresponding leak holes. A through-connector is provided, which is correspondingly installed in the leakage hole. The through-connector includes a vent valve and a connecting pipe connected together. The connecting pipe passes through the leakage hole to connect the internal space and the external space of the simulation shell. The vent valve is located outside the simulation shell.

2. The nuclear power plant containment leakage simulation system according to claim 1, characterized in that, The nuclear power plant containment leakage simulation system also includes a pressurization connector that penetrates the simulated containment structure.

3. The nuclear power plant containment leakage simulation system according to claim 2, characterized in that, The nuclear power plant containment leakage simulation system also includes gas cylinders; The through connector also includes an air inflator valve and a bottle valve, wherein the air inflator valve is connected to the interior of the simulated housing; The gas cylinder opening is connected to a first interface and multiple second interfaces, and the multiple second interfaces correspond one-to-one with and are connected to the cylinder valves of the multiple through connectors; The pressurization connector includes a pressurization tube, a third interface, and a fourth interface. The pressurization tube passes through the simulation housing, the third interface communicates with the interior of the simulation housing, and the fourth interface is connected to the first interface.

4. The nuclear power plant containment leakage simulation system according to any one of claims 1 to 3, characterized in that, The nuclear power plant containment leakage simulation system also includes a pressure testing unit and a safety unit; The pressure detection unit includes a detection tube and a pressure gauge connected together. The detection tube passes through the simulation housing, and the pressure gauge is located outside the simulation housing. The safety unit includes a safety pipe and a safety valve connected together. The safety pipe passes through the simulation housing, and the safety valve is located outside the simulation housing.

5. The nuclear power plant containment leakage simulation system according to claim 4, characterized in that, The detection tube penetrates the dome shell, and the safety tube penetrates the dome shell.

6. The nuclear power plant containment leakage simulation system according to any one of claims 1 to 3, characterized in that, The nuclear power plant containment leakage simulation system also includes an electrical penetration device that passes through the simulated containment, and the sensor cables pass through and are sealed in the electrical penetration device.

7. The nuclear power plant containment leakage simulation system according to any one of claims 1 to 3, characterized in that, The simulated outer shell has a container door.

8. The nuclear power plant containment leakage simulation system according to any one of claims 1 to 3, characterized in that, The nuclear power plant containment leakage simulation system also includes multiple gas flow meters, each of which corresponds to and is connected to a multiple venting valve.

9. The nuclear power plant containment leakage simulation system according to any one of claims 1 to 3, characterized in that, The simulated shell includes an inner liner and a casting layer. The casting layer surrounds the inner liner and is divided into connecting parts of different thicknesses from top to bottom along the vertical direction. Each connecting part and the corresponding inner liner form at least two sidewall shells arranged from top to bottom.

10. A method for simulating a nuclear power plant containment leak, comprising using the nuclear power plant containment leak simulation system according to any one of claims 1 to 9 to simulate the sensor signal of the leak, characterized in that, The method for simulating containment leakage in nuclear power plants includes the following steps: Close all the aforementioned vent valves and pressurize the interior of the simulated housing; When the vent valve corresponding to any of the leak holes is opened, the gas inside the simulated housing leaks outward through the through connector corresponding to the leak hole, and the sensor corresponding to the leak hole collects leakage data during the leakage process. Leakage tests were sequentially performed on multiple leak holes of different inner diameters in one of the housings, and leakage data of the corresponding sensors were collected; Leakage tests were conducted on the leak holes with the same inner diameter selected in each of the housings, and data from the corresponding sensors were collected. After the data collection by the sensor is completed, the pressure inside the simulated housing is released.

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