Flow measurement system and method for compact reactor coolant system

Abstract

The application provides a flow measurement system and a measurement method for a compact reactor coolant system. The flow measurement system is connected with an inlet chamber and an outlet chamber of a steam generator through a bypass pipe, and is matched with a first detection assembly and a second detection assembly for detecting the pressure and temperature of the chamber, a flow meter on the bypass pipe and a processing unit. The flow measurement system realizes accurate measurement of the coolant system flow by relying on the pressure, temperature and bypass flow multi-parameter acquisition and comprehensive calculation of the parallel flow channel.

Description

Technical Field

[0001] This invention relates to the field of compact reactor coolant systems, and more specifically to a flow measurement system and method for compact reactor coolant systems. Background Technology

[0002] As an important type of small reactor, compact reactors have become a research and application hotspot in the nuclear power field due to their advantages of compact structure, high equipment integration and small footprint. Compared with traditional large pressurized water reactors, their coolant system eliminates the main pipeline design, which greatly simplifies the system structure. However, this design also causes traditional flow meters to lose their applicable installation and measurement conditions, making the flow measurement of the coolant system a technical challenge.

[0003] The flow rate of the reactor coolant system is a core parameter for monitoring the reactor's operating status. It not only directly characterizes the system's forced circulation operating condition and determines the effective heat removal efficiency from the reactor core, but it is also a key safety parameter that triggers reactor shutdown and the activation of dedicated safety facilities. Its accurate measurement is a necessary prerequisite for ensuring the stable operation of the reactor and nuclear safety.

[0004] In existing technologies, flow measurement schemes for reactor coolant systems are all based on traditional reactor designs with main pipes, which cannot be adapted to the main pipe-less structure of compact reactor coolant systems. Furthermore, conventional pipeless flow measurement methods are insufficient to meet the stringent requirements of the nuclear power industry for measurement accuracy, stability, and safety. Without suitable flow measurement methods, reliable flow signals cannot be provided for the operation control and safety protection of compact reactors, and critical safety margins will be lost under transient and accident conditions.

[0005] Based on this, the inventors of this application propose a flow measurement system and method for a compact reactor coolant system, in order to solve one or more of the above-mentioned technical problems. Summary of the Invention

[0006] The present invention solves the above-mentioned technical problems through the following technical solution: The first aspect of the present invention provides a flow measurement system for a compact reactor coolant system, comprising: a bypass pipe, a first detection component, a second detection component, a flow meter, and a processing unit; One end of the bypass pipe is connected to the inlet chamber of the steam generator, and the other end is connected to the outlet chamber of the steam generator. The first detection component includes a first pressure detection component and a first temperature detection component. The first pressure detection component is used to measure the pressure of the inlet chamber of the steam generator and output a first pressure detection signal. The first temperature detection component is used to detect the temperature of the inlet chamber of the steam generator and output a first temperature detection signal. The second detection component includes a second pressure detection component and a second temperature detection component. The second pressure detection component is used to measure the pressure of the outlet chamber of the steam generator and output a second pressure detection signal. The second temperature detection component is used to detect the temperature of the outlet chamber of the steam generator and output a second temperature detection signal. The flow meter is installed on the bypass pipe and is used to detect the flow rate of the medium in the bypass pipe and output a bypass flow detection signal; The processing unit is connected to the first detection component, the second detection component, and the flow meter signal respectively. The processing unit is used to receive the first pressure detection signal, the first temperature detection signal, the second pressure detection signal, the second temperature detection signal, and the bypass flow detection signal to calculate the total flow rate of the compact reactor coolant system.

[0007] According to one embodiment of the present invention, the first pressure detection component includes at least two first pressure detection elements, wherein the at least two first pressure detection elements are arranged in parallel and are all signal-connected to the processing unit; The second pressure detection component includes at least two second pressure detection elements, which are arranged in parallel and are all signal-connected to the processing unit.

[0008] According to an embodiment of the present invention, an inlet pressure processor is further provided between the first pressure detection component and the processing unit. The inlet pressure processor is signal connected to each of the first pressure detection components and the processing unit respectively. The inlet pressure processor is used to receive and process the detection signals of the first pressure detection components. An outlet pressure processor is further provided between the second pressure detection component and the processing unit. The outlet pressure processor is signal-connected to each of the second pressure detection components and the processing unit, and is used to receive and process the detection signals of the second pressure detection components.

[0009] According to one embodiment of the present invention, a first alarm unit is connected to one side of the inlet pressure processor. The first alarm unit is used to receive a fault trigger signal of the inlet pressure processor and issue an alarm prompt. A second alarm unit is connected to one side of the outlet pressure processor. The second alarm unit is used to receive the fault trigger signal of the outlet pressure processor and issue an alarm prompt.

[0010] According to one embodiment of the present invention, both the inlet pressure processor and the outlet pressure processor are provided with a pressure deviation determination module; The pressure deviation determination module within the inlet pressure processor is used to compare whether the deviation of the detection values ​​of at least two of the first pressure detection elements exceeds a preset threshold; if it does, an inlet pressure fault trigger signal is output. The pressure deviation determination module within the outlet pressure processor is used to compare whether the deviation of the detection values ​​of at least two second pressure detection elements exceeds a preset threshold; if it does, an outlet pressure fault trigger signal is output.

[0011] According to one embodiment of the present invention, a display device is further included, the display device being connected to the processing unit; The display device is used to receive the total flow rate data signal of the compact reactor coolant system output by the processing unit and display the total flow rate in real time.

[0012] According to one embodiment of the present invention, the bypass pipe forms a parallel flow channel with the flow channel from the inlet chamber to the outlet chamber of the steam generator.

[0013] A second aspect of the invention also provides a compact reactor coolant system, including the flow measurement system for a compact reactor coolant system as described above.

[0014] The third invention also provides a compact reactor, comprising: a flow measurement system for a compact reactor coolant system as described above; or a compact reactor coolant system as described in claim 8.

[0015] The fourth invention also provides a flow measurement method for a compact reactor coolant system, characterized in that it employs the flow measurement system for a compact reactor coolant system as described above, and the measurement method includes: Step 1: Obtain the pressure and temperature values ​​of the steam generator inlet chamber through the first detection component, obtain the pressure and temperature values ​​of the steam generator outlet chamber through the second detection component, and simultaneously obtain the medium flow rate value in the bypass pipe through the flow meter on the bypass pipe. Step 2: The pressure and temperature values ​​of the inlet chamber and the outlet chamber, as well as the medium flow rate value of the bypass pipe, are transmitted to the processing unit. The processing unit, based on the same principle as the parallel pressure drop of the bypass pipe and the flow channel from the inlet chamber to the outlet chamber of the steam generator, performs pressure drop correction on the medium flow rate value by combining the resistance coefficients of the two, and performs temperature compensation by using the temperature values ​​of the first detection component and the second detection component, so as to calculate the total flow rate of the compact reactor coolant system.

[0016] The positive and progressive effects of this invention are as follows: This invention relates to a flow measurement system for a compact reactor coolant system. It connects the inlet and outlet chambers of the steam generator via a bypass pipe. It is equipped with a first and second detection component for detecting chamber pressure and temperature, as well as a flow meter and processing unit on the bypass pipe. By relying on the acquisition and comprehensive calculation of multiple parameters such as pressure, temperature and bypass flow in the parallel flow channel, it achieves accurate measurement of the coolant system flow. Attached Figure Description

[0017] The above and other features, properties and advantages of the present invention will become more apparent from the following description taken in conjunction with the accompanying drawings and embodiments, wherein: Figure 1 This is a schematic diagram of the flow measurement system for a compact reactor coolant system according to the present invention; Figure 2 This is a schematic diagram of the processing principle of the pressure deviation determination module of the inlet pressure processor of the present invention; Figure 3 This is a schematic diagram of the processing principle of the pressure deviation determination module of the outlet pressure processor of the present invention; Figure 4 This is a diagram illustrating the flow rate calculation process of the coolant system according to the present invention. Figure 5 This is a flowchart of the flow measurement method for a compact reactor coolant system according to the present invention.

[0018] 1. Bypass pipe; 2. First detection component; 21. First pressure detection component; 211. First pressure detection element; 22. First temperature detection element; 3. Second detection component; 31. Second pressure detection component; 311. Second pressure detection element; 32. Second temperature detection element; 4. Flow meter; 5. Processing unit; 51. Display device; 6. Steam generator; 61. Inlet chamber; 62. Outlet chamber; 7. Inlet pressure processor; 71. First alarm unit; 8. Outlet pressure processor; 81. Second alarm unit; 9. Pressure Deviation Judgment Module. Detailed Implementation

[0019] The present invention will be further described below with reference to specific embodiments and accompanying drawings. More details are set forth in the following description in order to provide a full understanding of the present invention. However, the present invention can obviously be implemented in many other ways different from those described herein. Those skilled in the art can make similar extensions and derivations based on actual application situations without departing from the spirit of the present invention. Therefore, the scope of protection of the present invention should not be limited by the content of this specific embodiment.

[0020] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application pertains; the terminology used herein is for the purpose of describing particular embodiments only and is not intended to limit the application; the terms “comprising” and “having”, and any variations thereof, in the specification, claims, and foregoing description of the drawings are intended to cover non-exclusive inclusion.

[0021] The compact reactor coolant system eliminates the main piping design, making the system structure more compact. The pressure vessel and steam generator 6 are connected only by a very short pipe. Conventional flow measurement devices such as orifice plate flow meters 4 require a certain length of straight pipe for accurate measurement. Therefore, existing measuring devices such as orifice plate flow meters 4 cannot meet the flow measurement requirements of the compact reactor coolant system.

[0022] Based on this, please refer to Figure 1 This application proposes a flow measurement system for a compact reactor coolant system, including a bypass pipe 1, a first detection component 2, a second detection component 3, a flow meter 4, and a processing unit 5.

[0023] One end of the bypass pipe 1 is connected to the inlet chamber 61 of the steam generator 6, and the other end is connected to the outlet chamber 62 of the steam generator 6. The bypass pipe 1 is arranged in parallel with the flow channel between the inlet chamber 61 and the outlet chamber 62 of the steam generator 6.

[0024] The first detection component 2 includes a first pressure detection component 21 and a first temperature detection component 22. The first pressure detection component 21 is used to measure the pressure of the inlet chamber 61 of the steam generator 6 and output a first pressure detection signal. The first temperature detection component 22 is used to detect the temperature of the inlet chamber 61 of the steam generator 6 and output a first temperature detection signal.

[0025] The second detection component 3 includes a second pressure detection component 31 and a second temperature detection component 32. The second pressure detection component 31 is used to measure the pressure of the outlet chamber 62 of the steam generator 6 and output a second pressure detection signal. The second temperature detection component 32 is used to detect the temperature of the outlet chamber 62 of the steam generator 6 and output a second temperature detection signal.

[0026] The flow meter 4 is installed on the bypass pipe 1 to detect the flow rate of the medium in the bypass pipe 1 and output the bypass flow detection signal.

[0027] The processing unit 5 is connected to the first detection component 2, the second detection component 3 and the flow meter 4 respectively. The processing unit 5 is used to receive the first pressure detection signal, the first temperature detection signal, the second pressure detection signal, the second temperature detection signal and the bypass flow detection signal. Based on the principle that the pressure drop of the parallel flow channels is the same, combined with the resistance coefficient of the bypass pipe 1 and the steam generator 6 flow channel, the bypass flow detection signal is corrected, and temperature compensation is performed through the first temperature detection signal and the second temperature detection signal to calculate the total flow of the compact reactor coolant system.

[0028] That is, because the bypass pipe 1 and the flow channels between the inlet chamber 61 and the outlet chamber 62 of the steam generator 6 are connected in parallel, the inlet and outlet pressure differences of these two flow channels are exactly the same. Combining the resistance coefficients of the bypass pipe 1 and the steam generator 6 flow channels, the flow rate ratio of the two flow channels can be calculated. The processing unit 5 first receives the actual flow rate measured by the flow meter 4 of the bypass pipe 1, and then calculates the flow rate of the steam generator 6 flow channel based on this ratio. The sum of the two flow channels is the total flow rate of the reactor coolant system. Meanwhile, the temperature of the coolant affects its physical properties and the actual flow rate. Therefore, the processing unit 5 adds the detected inlet and outlet temperature data for compensation and correction, eliminating errors caused by temperature, and finally calculates the accurate total flow rate of the coolant system.

[0029] In one embodiment, the first pressure detection component 21 includes at least two first pressure detection elements 211, which are connected in parallel and are all signal-connected to the processing unit 5; the second pressure detection component 31 includes at least two second pressure detection elements 311, which are connected in parallel and are all signal-connected to the processing unit 5.

[0030] By setting at least two first pressure detection elements 211 and at least two second pressure detection elements 311, it can serve as a redundant safety design and also improve the measurement accuracy of the pressure in the inlet chamber 61 and the outlet chamber 62 by averaging.

[0031] Furthermore, an inlet pressure processor 7 is provided between the first pressure detection component 21 and the processing unit 5. The inlet pressure processor 7 is signal-connected to each of the first pressure detection components 211 and the processing unit 5, and is used to receive and process the detection signals of the first pressure detection components 211. An outlet pressure processor 8 is provided between the second pressure detection component 31 and the processing unit 5. The outlet pressure processor 8 is signal-connected to each of the second pressure detection components 311 and the processing unit 5, and is used to receive and process the detection signals of the second pressure detection components 311.

[0032] Both the inlet pressure processor 7 and the outlet pressure processor 8 are equipped with a pressure deviation determination module 9. The pressure deviation determination module 9 in the inlet pressure processor 7 is used to compare whether the deviation of the detection values ​​of at least two first pressure detection elements 211 exceeds a preset threshold. If it exceeds the threshold, an inlet pressure fault trigger signal is output. The pressure deviation determination module 9 in the outlet pressure processor 8 is used to compare whether the deviation of the detection values ​​of at least two second pressure detection elements 311 exceeds a preset threshold. If it exceeds the threshold, an outlet pressure fault trigger signal is output.

[0033] Optionally, a first alarm unit 71 is connected to one side of the inlet pressure processor 7. The first alarm unit 71 is used to receive the fault trigger signal of the inlet pressure processor 7 and issue an alarm prompt. A second alarm unit 81 is connected to one side of the outlet pressure processor 8. The second alarm unit 81 is used to receive the fault trigger signal of the outlet pressure processor 8 and issue an alarm prompt.

[0034] Please refer to Figure 2 and Figure 3 Taking four first pressure detection elements 211 and four second pressure detection elements 311 as examples, the processing procedure of the pressure deviation judgment module 9 of the inlet pressure processor 7 is as follows: It receives the measured values ​​from the four first pressure detection elements 211 (P3A, P3B, P3C, and P3D). First, it selects P3A, P3B, and P3C to perform an algebraic average, and determines the difference between the average value and the measured values ​​of P3A, P3B, and P3C respectively. If the difference between the measured values ​​of P3A, P3B, and P3C and the average value is less than the target threshold, for example, 1%, then the algebraic average of the three is the first pressure detection signal value. If any of P3A, P3B, or P3C has a difference from the average value greater than the target threshold, then it selects the two measured values ​​whose absolute value of the difference from the average value decreases and performs an algebraic average with the measured value of P3D. If the difference between the measured value of P3D and the average value is less than the target threshold, for example, 1%, then the average value is used as the first pressure detection signal value; otherwise, if it is greater than the target threshold, an alarm signal is issued.

[0035] The processing procedure of the pressure deviation determination module 9 of the outlet pressure processor 8 (e.g.) Figure 3 The process is the same as that of the inlet pressure processor 7, and will not be described in detail here.

[0036] The alarm prompts mentioned above can be either buzzers or light alarms; there is no specific limitation here.

[0037] like Figure 1 As shown, a display device 51 is also connected to one side of the processing unit 5. The display device 51 is used to receive the total flow data signal of the compact reactor coolant system output by the processing unit 5 and display the total flow in real time.

[0038] like Figure 4 As shown, the flow rate measurement process of the coolant system in this application is as follows: Select the flow rate through the coolant system... Figure 2 The calculated algebraic average values ​​of two pressure measurements, P3 and P4, are used. P3 is the corrected pressure value of the inlet chamber 61 of the steam generator 6, and P4 is the corrected pressure value of the outlet chamber 62 of the steam generator 6. First, the theoretical flow rate of bypass pipe 1 is calculated using the pressure difference between P3 and P4. Then, the actual measured value of the flow meter 4 on bypass pipe 1 is used to correct this theoretical flow rate, resulting in the accurate actual flow rate of bypass pipe 1. Finally, a comprehensive compensation correction is performed using the resistance coefficient of bypass pipe 1, the flow channel resistance coefficient of steam generator 6, and the measured temperature values ​​of the first temperature sensor 22 and the second temperature sensor 32 to calculate the total flow rate of the reactor coolant system.

[0039] In other words, the measured value of flow meter 4 is easily affected by operating conditions and equipment errors. Therefore, this application combines the pressure difference calculation of the average pressure to perform double verification and precise correction on the measured value of flow meter 4, so that the flow data of bypass pipe 1 is more in line with the actual operating conditions of the reactor, and ultimately ensures the accuracy of the total flow meter 4 of the reactor coolant system.

[0040] The present invention also proposes a compact reactor coolant system, including the flow measurement system for a compact reactor coolant system as described above.

[0041] The present invention also proposes a compact reactor, comprising: the flow measurement system for a compact reactor coolant system as described above; or the compact reactor coolant system as described above.

[0042] Please refer to Figure 5 The present invention also proposes a flow measurement method for a compact reactor coolant system, characterized in that it employs the above-described flow measurement system for a compact reactor coolant system, and the measurement method includes: S1. Obtain the pressure and temperature values ​​of the inlet chamber of the steam generator through the first detection component, obtain the pressure and temperature values ​​of the outlet chamber of the steam generator through the second detection component, and simultaneously obtain the medium flow rate value in the bypass pipe through the flow meter on the bypass pipe. S2. The pressure and temperature values ​​of the inlet and outlet chambers, as well as the medium flow rate value of the bypass pipe, are transmitted to the processing unit. The processing unit, based on the same principle of parallel pressure drop in the bypass pipe and the flow channel from the inlet to the outlet chamber of the steam generator, performs pressure drop correction on the medium flow rate value by combining the resistance coefficients of the two, and performs temperature compensation by using the temperature values ​​of the first and second detection components, so as to calculate the total flow rate of the compact reactor coolant system.

[0043] The compact reactor coolant system flow measurement method proposed in this application first derives the theoretical flow rate of the bypass pipe based on the corrected average inlet and outlet pressure of the steam generator. Then, it combines the measured values ​​of the flow meter to accurately correct the theoretical flow rate. Subsequently, it integrates the flow channel resistance coefficient and temperature detection values ​​to complete the comprehensive compensation calculation. This not only makes up for the problem that the measured value of a single flow meter is easily affected by the complex operating conditions of nuclear power plants with high temperature and high pressure, but also makes the flow calculation closely match the actual operating conditions of the system throughout the process, effectively improving the accuracy and reliability of the bypass pipe flow data.

[0044] Meanwhile, this measurement method relies on the core principle of identical pressure drop in parallel flow channels, and is adapted to the structural characteristics of compact reactors without main pipelines and with short pipe connections between pressure vessels and steam generators. It solves the technical problem that traditional flow measurement methods cannot be applied, and the final calculated total flow of the coolant system has high accuracy and strong stability. It can provide accurate and reliable flow data support for reactor operation status monitoring, safety control, and safety decision-making under transient and accident conditions, fully meeting the stringent requirements for flow measurement in the nuclear power field.

[0045] In the description of the embodiments of this application, unless otherwise expressly specified and limited, the technical terms such as "installation", "connection", "joining", and "fixing" should be interpreted broadly. For example, they can refer to fixed connections, detachable connections, or integral connections; they can also refer to mechanical connections. For those skilled in the art, the specific meaning of the above terms in the embodiments of this application can be understood according to the specific circumstances.

[0046] This application uses specific terms to describe embodiments of the application. Terms such as "an embodiment," "one embodiment," and / or "some embodiments" refer to a particular feature, structure, or characteristic associated with at least one embodiment of the application. Therefore, it should be emphasized and noted that references to "an embodiment," "one embodiment," or "an alternative embodiment" in different locations throughout this specification do not necessarily refer to the same embodiment. Furthermore, certain features, structures, or characteristics in one or more embodiments of the application can be appropriately combined.

[0047] While the present invention has been disclosed above with reference to preferred embodiments, it is not intended to limit the invention. Any variations and modifications can be made by those skilled in the art without departing from the spirit and scope of the invention. Therefore, any modifications, equivalent changes, and alterations made to the above embodiments based on the technical essence of the present invention, without departing from the scope of the invention, fall within the protection scope defined by the claims of the present invention.

Claims

1. A flow measurement system for a compact reactor coolant system, characterized in that, include: Bypass pipe, first detection component, second detection component, flow meter and processing unit; One end of the bypass pipe is connected to the inlet chamber of the steam generator, and the other end is connected to the outlet chamber of the steam generator. The first detection component includes a first pressure detection component and a first temperature detection component. The first pressure detection component is used to measure the pressure of the inlet chamber of the steam generator and output a first pressure detection signal. The first temperature detection component is used to detect the temperature of the inlet chamber of the steam generator and output a first temperature detection signal. The second detection component includes a second pressure detection component and a second temperature detection component. The second pressure detection component is used to measure the pressure of the outlet chamber of the steam generator and output a second pressure detection signal. The second temperature detection component is used to detect the temperature of the outlet chamber of the steam generator and output a second temperature detection signal. The flow meter is installed on the bypass pipe and is used to detect the flow rate of the medium in the bypass pipe and output a bypass flow detection signal; The processing unit is connected to the first detection component, the second detection component, and the flow meter signal respectively. The processing unit is used to receive the first pressure detection signal, the first temperature detection signal, the second pressure detection signal, the second temperature detection signal, and the bypass flow detection signal to calculate the total flow rate of the compact reactor coolant system.

2. The flow measurement system for a compact reactor coolant system according to claim 1, characterized in that, The first pressure detection component includes at least two first pressure detection elements, which are arranged in parallel and are all signal-connected to the processing unit. The second pressure detection component includes at least two second pressure detection elements, which are arranged in parallel and are all signal-connected to the processing unit.

3. The flow measurement system for a compact reactor coolant system according to claim 2, characterized in that, An inlet pressure processor is further provided between the first pressure detection component and the processing unit. The inlet pressure processor is signal-connected to each of the first pressure detection components and the processing unit. The inlet pressure processor is used to receive and process the detection signals of the first pressure detection components. An outlet pressure processor is further provided between the second pressure detection component and the processing unit. The outlet pressure processor is signal-connected to each of the second pressure detection components and the processing unit, and is used to receive and process the detection signals of the second pressure detection components.

4. The flow measurement system for a compact reactor coolant system according to claim 3, characterized in that, A first alarm unit is connected to one side of the inlet pressure processor. The first alarm unit is used to receive the fault trigger signal of the inlet pressure processor and issue an alarm prompt. A second alarm unit is connected to one side of the outlet pressure processor. The second alarm unit is used to receive the fault trigger signal of the outlet pressure processor and issue an alarm prompt.

5. The flow measurement system for a compact reactor coolant system according to claim 3, characterized in that, Both the inlet pressure processor and the outlet pressure processor are equipped with a pressure deviation determination module. The pressure deviation determination module within the inlet pressure processor is used to compare whether the deviation of the detection values ​​of at least two of the first pressure detection elements exceeds a preset threshold. If the pressure exceeds the limit, an inlet pressure fault trigger signal will be output. The pressure deviation determination module within the outlet pressure processor is used to compare whether the deviation of the detection values ​​of at least two second pressure detection elements exceeds a preset threshold. If the pressure exceeds the limit, an outlet pressure fault trigger signal will be output.

6. The flow measurement system for a compact reactor coolant system according to claim 1, characterized in that, It also includes a display device, which is connected to the processing unit; The display device is used to receive the total flow rate data signal of the compact reactor coolant system output by the processing unit and display the total flow rate in real time.

7. The flow measurement system for a compact reactor coolant system according to claim 1, characterized in that, The bypass pipe forms a parallel flow channel with the flow channel from the inlet chamber to the outlet chamber of the steam generator.

8. A compact reactor coolant system, characterized in that, Includes the flow measurement system for a compact reactor coolant system as described in any one of claims 1-7.

9. A compact reactor, characterized in that, include: The flow measurement system for a compact reactor coolant system as described in any one of claims 1-7; Or the compact reactor coolant system as described in claim 8.

10. A method for measuring the flow rate of a compact reactor coolant system, characterized in that, The flow measurement system for a compact reactor coolant system as described in any one of claims 1-7, wherein the measurement method comprises: Step 1: Obtain the pressure and temperature values ​​of the steam generator inlet chamber through the first detection component, obtain the pressure and temperature values ​​of the steam generator outlet chamber through the second detection component, and simultaneously obtain the medium flow rate value in the bypass pipe through the flow meter on the bypass pipe. Step 2: The pressure and temperature values ​​of the inlet chamber and the outlet chamber, as well as the medium flow rate value of the bypass pipe, are transmitted to the processing unit. The processing unit, based on the same principle as the parallel pressure drop of the bypass pipe and the flow channel from the inlet chamber to the outlet chamber of the steam generator, performs pressure drop correction on the medium flow rate value by combining the resistance coefficients of the two, and performs temperature compensation by using the temperature values ​​of the first detection component and the second detection component, so as to calculate the total flow rate of the compact reactor coolant system.

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