Fault detection method, device and equipment of nuclear power station cooling system and medium

Abstract

The invention discloses a fault detection method, device and equipment for a nuclear power station cooling system and a medium, and relates to the technical field of nuclear power station fault detection. The method comprises the following steps: acquiring coolant standard data of a main circulating pump in a nuclear power plant cooling system; monitoring actual coolant data of the main circulating pump; according to the coolant standard data of the main circulating pump and the coolant actual data of the main circulating pump, performing fault detection on the main circulating pipeline in the nuclear power station cooling system to obtain a detection result of the main circulating pipeline in the nuclear power station cooling system; and determining a fault detection result of the nuclear power station cooling system according to the detection result of the main circulating pipeline. According to the technical scheme of the embodiment of the invention, the detection efficiency and the detection accuracy of the nuclear power station cooling system are improved.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear power plant fault detection, and in particular to a fault detection method, device, equipment and medium for a nuclear power plant cooling system. Background Art

[0002] The cooling system of a nuclear power plant is a vital component of the plant. It is mainly used to remove the large amount of heat generated by the nuclear reactor during operation to ensure the safe and stable operation of the reactor.

[0003] In the prior art, staff members mainly check the operating parameters of each component in the cooling system one by one and manually judge the actual working condition of the cooling system. This has the defects of low detection efficiency of the cooling system and poor accuracy of the detection results. Summary of the Invention

[0004] The present invention provides a method, device, equipment and medium for fault detection of a nuclear power plant cooling system, so as to improve the efficiency and accuracy of fault detection.

[0005] In a first aspect, the present invention provides a method for detecting a fault in a cooling system of a nuclear power plant, comprising:

[0006] Obtain coolant standard data for the main circulation pump in the nuclear power plant cooling system;

[0007] Monitoring actual coolant data of the main circulation pump;

[0008] performing fault detection on the main circulation pipeline in the cooling system of the nuclear power plant according to the coolant standard data of the main circulation pump and the coolant actual data of the main circulation pump, and obtaining a detection result of the main circulation pipeline in the cooling system of the nuclear power plant;

[0009] The fault detection result of the nuclear power plant cooling system is determined based on the detection result of the main circulation pipeline.

[0010] In a second aspect, the present invention further provides a fault detection device for a nuclear power plant cooling system, comprising:

[0011] A data acquisition module is used to obtain coolant standard data of the main circulation pump in the cooling system of the nuclear power plant;

[0012] A data monitoring module, used for monitoring actual coolant data of the main circulation pump;

[0013] a pipeline detection module, configured to perform fault detection on the main circulation pipeline in the cooling system of the nuclear power plant according to the coolant standard data of the main circulation pump and the coolant actual data of the main circulation pump, and obtain a detection result of the main circulation pipeline in the cooling system of the nuclear power plant;

[0014] The cooling system detection module is used to determine the fault detection result of the nuclear power plant cooling system according to the detection result of the main circulation pipeline.

[0015] In a third aspect, an embodiment of the present invention further provides a fault detection device for a nuclear power plant cooling system, comprising:

[0016] at least one processor; and

[0017] a memory communicatively coupled to at least one processor; wherein

[0018] The memory stores instructions that can be executed by at least one processor. The instructions are executed by the at least one processor so that the at least one processor can execute the fault detection method for the nuclear power plant cooling system provided by any embodiment of the present invention.

[0019] In a fourth aspect, an embodiment of the present invention further provides a computer-readable storage medium storing computer instructions, which are used to enable a processor to implement the fault detection method for a nuclear power plant cooling system of any embodiment of the present invention when executed.

[0020] The technical solution of the embodiment of the present invention obtains the coolant standard data of the main circulation pump in the nuclear power plant cooling system; monitors the actual coolant data of the main circulation pump; performs fault detection on the main circulation pipeline in the nuclear power plant cooling system based on the coolant standard data of the main circulation pump and the actual coolant data of the main circulation pump, and obtains the detection result of the main circulation pipeline in the nuclear power plant cooling system; determines the fault detection result of the nuclear power plant cooling system based on the detection result of the main circulation pipeline. Compared with the solution of manually judging the working condition of the cooling system in the prior art, this technical solution realizes the automatic fault detection of the nuclear power plant cooling system, improves the accuracy and efficiency of the fault detection of the nuclear power plant cooling system; through the automatic cooling system fault detection, it is possible to detect and prevent possible nuclear power plant safety problems in a timely manner, thereby improving the safety and operational reliability of the nuclear power plant.

[0021] It should be understood that the content described in this section is not intended to identify the key or important features of the embodiments of the present invention, nor is it intended to limit the scope of the present invention. Other features of the present invention will become readily understood through the following description. BRIEF DESCRIPTION OF THE DRAWINGS

[0022] In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the following briefly introduces the drawings required for use in the description of the embodiments. Obviously, the drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without creative work.

[0023] Figure 1A This is a flow chart of a method for detecting a fault in a nuclear power plant cooling system according to a first embodiment of the present invention;

[0024] Figure 1B This is a schematic structural diagram of a nuclear power plant equipped with a cooling system according to a first embodiment of the present invention;

[0025] Figure 2 This is a flow chart of a method for detecting a fault in a nuclear power plant cooling system according to a second embodiment of the present invention;

[0026] Figure 3 This is a schematic structural diagram of a fault detection device for a nuclear power plant cooling system provided in accordance with a third embodiment of the present invention;

[0027] Figure 4 1 is a schematic structural diagram of a nuclear power plant cooling system fault detection device for implementing a nuclear power plant cooling system fault detection method according to an embodiment of the present invention;

[0028] Figure 5 It is a structural diagram of an electronic device for implementing a fault detection method for a nuclear power plant cooling system according to an embodiment of the present invention. DETAILED DESCRIPTION

[0029] In order to enable those skilled in the art to better understand the solutions of the present invention, the technical solutions in the embodiments of the present invention will be clearly and completely described below in conjunction with the drawings in the embodiments of the present invention. Obviously, the embodiments described are only part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without making creative efforts should fall within the scope of protection of the present invention.

[0030] It should be noted that the terms "first" and "second" and the like in the specification and claims of the present invention and the above-mentioned drawings are used to distinguish similar objects and are not necessarily used to describe a specific order or precedence. It should be understood that the numbers used in this way are interchangeable where appropriate so that the embodiments of the present invention described herein can be implemented in an order other than those illustrated or described herein. In addition, the terms "including" and "having" and any variations thereof are intended to cover non-exclusive inclusions, for example, a process, method, system, product or apparatus comprising a series of steps or units is not necessarily limited to those steps or units clearly listed, but may include other steps or units that are not clearly listed or inherent to these processes, methods, products or apparatus.

[0031] In the technical solutions of the embodiments of the present invention, the acquisition, storage and application of the information to be displayed, etc., all comply with the provisions of relevant laws and regulations and do not violate public order and good morals.

[0032] Example 1

[0033] Figure 1A A flowchart of a fault detection method for a nuclear power plant cooling system provided in Example 1 of the present invention is applicable to situations where fault detection is performed on a nuclear power plant cooling system. The method can be performed by a fault detection device for a nuclear power plant cooling system. The fault detection device for a nuclear power plant cooling system can be implemented in the form of hardware and / or software and specifically configured in a fault detection device for a nuclear power plant cooling system, such as a server.

[0034] Figure 1B This is a schematic diagram of the structure of a nuclear power plant equipped with a cooling system. Figure 1B As shown, the nuclear power plant includes a nuclear reactor core 500 and a cooling system. The cooling system includes a primary circulation pump 100, a primary circulation pipeline 110, a heat exchanger 200, an auxiliary circulation pump 300, a cooling tower 400, and the nuclear reactor core 500. Specifically, the primary circulation pump 100 pumps coolant from the nuclear reactor core 500 through the primary circulation pipeline 110 to the heat exchanger 200. The heat exchanger 200 performs heat exchange on the coolant, producing steam, which is then supplied to corresponding devices. The auxiliary circulation pump 300 transports the heat-exchanged coolant to the cooling tower 400 for further cooling. The cooling tower 400 then re-injects the cooled coolant into the nuclear reactor core 500 through the primary circulation pump 100 to cool the nuclear reactor core 500.

[0035] See also Figure 1A The fault detection method of the nuclear power plant cooling system shown includes:

[0036] S101. Obtain coolant standard data of a main circulation pump in a nuclear power plant cooling system.

[0037] S102: Monitor actual coolant data of the main circulation pump.

[0038] S103 , performing fault detection on the main circulation pipeline in the nuclear power plant cooling system according to the coolant standard data and the coolant actual data of the main circulation pump, and obtaining a detection result of the main circulation pipeline in the nuclear power plant cooling system.

[0039] S104. Determine the fault detection result of the nuclear power plant cooling system according to the detection result of the main circulation pipeline.

[0040] In this embodiment, the standard coolant data of the main circulation pump may be the status data of the coolant in the main circulation pump when the nuclear power plant cooling system is fault-free; and the actual coolant data of the main circulation pump may be the status data of the coolant in the main circulation pump obtained through actual monitoring. The status data may include, but is not limited to, temperature, flow rate, and pressure.

[0041] It should be noted that the coolant standard data of the main circulation pump can be independently set by technical personnel based on actual needs or practical experience; or the status data of the coolant in the main circulation pump can be collected when the nuclear power plant cooling system is fault-free, and the collected data can be determined as the coolant standard data of the main circulation pump.

[0042] Specifically, the method includes obtaining standard coolant data of a main circulation pump in a nuclear power plant cooling system; monitoring actual coolant data of the main circulation pump; employing a certain algorithm to perform fault detection on the main circulation pipeline in the nuclear power plant cooling system based on the standard coolant data and actual coolant data of the main circulation pump, thereby obtaining a detection result of the main circulation pipeline in the nuclear power plant cooling system; if the detection result of the main circulation pipeline indicates a main circulation pipeline failure, then determining that the fault detection result of the nuclear power plant cooling system is a fault; if the detection result of the main circulation pipeline indicates that the main circulation pipeline is normal, then determining that the fault detection result of the nuclear power plant cooling system is normal. In one specific embodiment, after obtaining the fault detection result of the nuclear power plant cooling system, the fault detection result of the nuclear power plant cooling system may also be sent to technical personnel so that the technical personnel can promptly understand and make appropriate decisions and measures based on the fault detection result of the nuclear power plant cooling system.

[0043] Optionally, the standard data of the coolant of the main circulation pump include: the set temperature of the coolant at the output end of the main circulation pump, the set flow rate of the coolant at the output end of the main circulation pump, and the set pressure of the coolant at the output end of the main circulation pump; the actual data of the coolant of the main circulation pump include: the actual temperature of the coolant at the output end of the main circulation pump, the actual flow rate of the coolant at the output end of the main circulation pump, and the actual pressure of the coolant at the output end of the main circulation pump.

[0044] The output end of the main circulation pump may be the end of the main circulation pump that outputs the coolant. The coolant set temperature at the output end of the main circulation pump may be set by a technician, and is the coolant temperature at the output end of the main circulation pump when the nuclear power plant is cooling without any faults. The coolant set temperature at the output end of the main circulation pump may be set by a technician, and is the coolant temperature at the output end of the main circulation pump when the nuclear power plant is cooling without any faults. The coolant set flow rate at the output end of the main circulation pump may be set by a technician, and is the coolant flow rate at the output end of the main circulation pump when the nuclear power plant is cooling without any faults. The coolant set pressure at the output end of the main circulation pump may be set by a technician, and is the coolant pressure at the output end of the main circulation pump when the nuclear power plant is cooling without any faults. The actual coolant temperature at the output end of the main circulation pump may be the coolant temperature at the output end of the main circulation pump obtained by actual monitoring. The actual coolant flow rate at the output end of the main circulation pump may be the coolant flow rate at the output end of the main circulation pump obtained by actual monitoring. The actual coolant pressure at the output end of the main circulation pump may be the coolant pressure at the output end of the main circulation pump obtained by actual monitoring.

[0045] It is understandable that the above-mentioned optional technical solution can combine multi-dimensional coolant status data including temperature, flow rate and pressure to comprehensively determine the detection results of the main circulation pipeline, thereby improving the accuracy of the detection results of the main circulation pipeline.

[0046] The technical solution of the embodiment of the present invention obtains the coolant standard data of the main circulation pump in the nuclear power plant cooling system; monitors the actual coolant data of the main circulation pump; performs fault detection on the main circulation pipeline in the nuclear power plant cooling system based on the coolant standard data of the main circulation pump and the actual coolant data of the main circulation pump, and obtains the detection result of the main circulation pipeline in the nuclear power plant cooling system; determines the fault detection result of the nuclear power plant cooling system based on the detection result of the main circulation pipeline. Compared with the solution of manually judging the working condition of the cooling system in the prior art, this technical solution realizes the automatic fault detection of the nuclear power plant cooling system, improves the accuracy and efficiency of the fault detection of the nuclear power plant cooling system; through the automatic cooling system fault detection, it is possible to detect and prevent possible nuclear power plant safety problems in a timely manner, thereby improving the safety and operational reliability of the nuclear power plant.

[0047] Example 2

[0048] Figure 2 This is a flow chart of a fault detection method for a nuclear power plant cooling system provided in the second embodiment of the present invention. Based on the technical solutions of the above embodiments, the embodiment of the present invention optimizes and improves the operation of determining the detection results of the main circulation pipeline.

[0049] Further, “perform fault detection on the main circulation pipeline in the cooling system of the nuclear power plant according to the coolant standard data of the main circulation pump and the actual coolant data of the main circulation pump, and obtain the detection result of the main circulation pipeline in the cooling system of the nuclear power plant” is refined into “determine the fault index value of the main circulation pipeline according to the coolant set temperature at the output end of the main circulation pump, the coolant set flow rate at the output end of the main circulation pump, the coolant set pressure at the output end of the main circulation pump, the actual coolant temperature at the output end of the main circulation pump, the actual coolant flow rate at the output end of the main circulation pump and the actual coolant pressure at the output end of the main circulation pump; perform fault detection on the main circulation pipeline according to the fault index value of the main circulation pipeline and the fault index threshold of the main circulation pipeline, and determine the detection result of the main circulation pipeline”, so as to improve the target color determination operation.

[0050] It should be noted that for the parts not described in detail in the embodiments of the present invention, reference can be made to the description of the aforementioned embodiments.

[0051] See also Figure 2 The fault detection method of the nuclear power plant cooling system shown includes:

[0052] S201. Obtain coolant standard data of a main circulation pump in a nuclear power plant cooling system.

[0053] S202: Monitor actual coolant data of the main circulation pump.

[0054] S203. Determine the fault index value of the main circulation pipeline according to the coolant set temperature at the output end of the main circulation pump, the coolant set flow rate at the output end of the main circulation pump, the coolant set pressure at the output end of the main circulation pump, the coolant actual temperature at the output end of the main circulation pump, the coolant actual flow rate at the output end of the main circulation pump, and the coolant actual pressure at the output end of the main circulation pump.

[0055] S204: Perform fault detection on the main circulation pipeline according to the fault index value and the fault index threshold of the main circulation pipeline, and determine the detection result of the main circulation pipeline.

[0056] S205. Determine the fault detection result of the nuclear power plant cooling system according to the detection result of the main circulation pipeline.

[0057] In this embodiment, the main circulation pipeline fault index value can be used to measure the normal operation of the nuclear power plant's main circulation pipeline, that is, the safe operation of the main circulation pipeline. The main circulation pipeline fault index value can reflect the degree of deviation between the actual state of the main circulation pipeline in the nuclear power plant's cooling system and the set normal state. The main circulation pipeline fault index threshold value can be independently set by technical personnel based on the coolant material properties and the actual conditions of the nuclear power plant.

[0058] Specifically, a certain algorithm is adopted to determine the fault index value of the main circulation pipeline according to the coolant set temperature at the output end of the main circulation pump, the coolant set flow rate at the output end of the main circulation pump, the coolant set pressure at the output end of the main circulation pump, the coolant actual temperature at the output end of the main circulation pump, the coolant actual flow rate at the output end of the main circulation pump and the coolant actual pressure at the output end of the main circulation pump; if the fault index value of the main circulation pipeline is greater than or equal to the fault index threshold value of the main circulation pipeline, then the fault detection result of the nuclear power plant cooling system is determined to be a fault; if the fault index value of the main circulation pipeline is less than the fault index value of the main circulation pipeline, then the fault detection result of the nuclear power plant cooling system is determined to be normal.

[0059] Optionally, determining a fault index value of the main circulation pipeline according to a set coolant temperature at the output end of the main circulation pump, a set coolant flow rate at the output end of the main circulation pump, a set coolant pressure at the output end of the main circulation pump, an actual coolant temperature at the output end of the main circulation pump, an actual coolant flow rate at the output end of the main circulation pump, and an actual coolant pressure at the output end of the main circulation pump includes:

[0060] According to the coolant set temperature at the output end of the main circulation pump and the actual coolant temperature at the output end of the main circulation pump, the main circulation pipeline is subjected to temperature fault detection to obtain the temperature deviation index value of the main circulation pipeline; according to the coolant set flow rate at the output end of the main circulation pump and the actual coolant flow rate at the output end of the main circulation pump, the main circulation pipeline is subjected to flow velocity fault detection to obtain the flow velocity deviation index value of the main circulation pipeline; according to the coolant set pressure at the output end of the main circulation pump and the actual coolant pressure at the output end of the main circulation pump, the main circulation pipeline is subjected to pressure fault detection to obtain the pressure deviation index value of the main circulation pipeline; according to the temperature deviation index value of the main circulation pipeline, the flow velocity deviation index value of the main circulation pipeline and the pressure deviation index value of the main circulation pipeline, the fault index value of the main circulation pipeline is determined.

[0061] Among them, the temperature deviation index value of the main circulation pipeline can be used to characterize the degree to which the actual temperature of the coolant at the output end of the main circulation pipeline deviates from the set temperature of the coolant at the output end of the main circulation pipeline; the flow rate deviation index value of the main circulation pipeline can be used to characterize the degree to which the actual flow rate of the coolant at the output end of the main circulation pipeline deviates from the set flow rate of the coolant at the output end of the main circulation pipeline; the pressure deviation index value of the main circulation pipeline can be used to characterize the degree to which the actual pressure of the coolant at the output end of the main circulation pipeline deviates from the set pressure of the coolant at the output end of the main circulation pipeline.

[0062] Specifically, the absolute value of the temperature difference between the set coolant temperature at the output end of the main circulation pump and the actual coolant temperature at the output end of the main circulation pump is determined as the temperature deviation index value; the absolute value of the flow rate difference between the set coolant flow rate at the output end of the main circulation pump and the actual coolant flow rate at the output end of the main circulation pump is determined as the flow rate deviation index value; the absolute value of the pressure difference between the set coolant pressure at the output end of the main circulation pump and the actual coolant pressure at the output end of the main circulation pump is determined; the pressure ratio between the absolute value of the pressure difference and the set coolant pressure at the output end of the main circulation pump is determined as the pressure deviation index value; the fault index value of the main circulation pipeline is determined according to the temperature deviation index value, the flow rate deviation index value and the pressure deviation index value of the main circulation pipeline; illustratively, the fault index value of the main circulation pipeline can be determined by the following formula:

[0063]

[0064] Among them, Q pipeb Indicates the fault index value of the main circulation pipeline; Tout s Indicates the actual temperature of the coolant at the output end of the main circulation pump; Tout r Indicates the coolant set temperature at the output end of the main circulation pump; Vout s Indicates the actual flow rate of the coolant at the output end of the main circulation pump; Vout r Indicates the coolant set flow rate at the output end of the main circulation pump; Pouts Indicates the actual pressure of the coolant at the outlet of the main circulation pump; Pout r Indicates the coolant set pressure at the output of the main circulation pump.

[0065] It can be understood that by adopting the above technical solution, the temperature deviation index value, flow rate deviation index value and pressure deviation index value of the main circulation pipeline are determined respectively, and then the fault index value of the main circulation pipeline is comprehensively determined through the temperature deviation index value of different dimensions, the flow rate deviation index value of the main circulation pipeline and the pressure deviation index value of the main circulation pipeline, thereby improving the accuracy of the fault detection results of the main circulation pipeline.

[0066] The technical solution in the embodiment of the present invention determines the fault index value of the main circulation pipeline according to the coolant set temperature at the output end of the main circulation pump, the coolant set flow rate at the output end of the main circulation pump, the coolant set pressure at the output end of the main circulation pump, the coolant actual temperature at the output end of the main circulation pump, the coolant actual flow rate at the output end of the main circulation pump and the coolant actual pressure at the output end of the main circulation pump; according to the fault index value of the main circulation pipeline and the fault index threshold of the main circulation pipeline, the main circulation pipeline is fault detected to determine the detection result of the main circulation pipeline, and the fault index value of the main circulation pipeline can be comprehensively and comprehensively determined through coolant data of different dimensions such as temperature, flow rate and pressure, thereby improving the accuracy of the fault result of the main circulation pipeline.

[0067] Example 3

[0068] Figure 3 This is a flow chart of a fault detection method for a nuclear power plant cooling system provided by the third embodiment of the present invention. This embodiment of the present invention is based on the technical solutions of the above embodiments and is additionally optimized.

[0069] Furthermore, the following is added: "obtaining standard data of the environment in which the heat exchanger is located and standard data of the coolant of the heat exchanger in the cooling system of the nuclear power plant; monitoring actual data of the environment in which the heat exchanger is located and actual data of the coolant of the heat exchanger; performing fault detection on the heat exchanger based on the standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, standard data of the coolant of the heat exchanger, actual data of the coolant of the heat exchanger, actual data of the coolant of the main circulation pump, specific heat capacity of the coolant and maximum heat transfer rate of the heat exchanger to obtain fault detection results of the heat exchanger; determining final detection results of the cooling system of the nuclear power plant based on the fault detection results of the heat exchanger and the fault detection results of the cooling system of the nuclear power plant" to improve the fault detection operation of the cooling system of the nuclear power plant.

[0070] It should be noted that for the parts not described in detail in the embodiments of the present invention, reference can be made to the description of the aforementioned embodiments.

[0071] See also Figure 3The fault detection method of the nuclear power plant cooling system shown includes:

[0072] S301. Obtain coolant standard data of the main circulation pump in the cooling system of the nuclear power plant.

[0073] S302: Monitor actual coolant data of the main circulation pump.

[0074] S303. Determine the fault index value of the main circulation pipeline according to the coolant set temperature at the output end of the main circulation pump, the coolant set flow rate at the output end of the main circulation pump, the coolant set pressure at the output end of the main circulation pump, the coolant actual temperature at the output end of the main circulation pump, the coolant actual flow rate at the output end of the main circulation pump and the coolant actual pressure at the output end of the main circulation pump.

[0075] S304: Perform fault detection on the main circulation pipeline according to the fault index value and the fault index threshold of the main circulation pipeline, and determine the detection result of the main circulation pipeline.

[0076] S305: Determine the fault detection result of the nuclear power plant cooling system according to the detection result of the main circulation pipeline.

[0077] S306: Obtain standard data of the environment in which the heat exchanger is located and standard data of the coolant of the heat exchanger in the cooling system of the nuclear power plant.

[0078] S307: Monitor actual data of the environment in which the heat exchanger is located and actual data of the coolant in the heat exchanger.

[0079] S308. Perform fault detection on the heat exchanger based on the standard data of the environment in which the heat exchanger is located, the actual data of the environment in which the heat exchanger is located, the standard data of the coolant of the heat exchanger, the actual data of the coolant of the heat exchanger, the actual data of the coolant of the main circulation pump, the specific heat capacity of the coolant and the maximum heat transfer rate of the heat exchanger to obtain a fault detection result of the heat exchanger.

[0080] S309: Determine a final detection result of the nuclear power plant cooling system based on the heat exchanger fault detection result and the nuclear power plant cooling system fault detection result.

[0081] In this embodiment, the standard data for the heat exchanger's environment may be environmental data of the environment surrounding the heat exchanger, provided that the heat exchanger operates normally. The standard data for the heat exchanger's environment may include, but is not limited to, a set temperature and standard humidity for the heat exchanger's environment. The standard data for the heat exchanger's coolant may be state data of the coolant in the heat exchanger, provided that the nuclear power plant's cooling system operates normally.

[0082] The actual data of the heat exchanger's environment can be obtained through actual monitoring, and include actual data of the environment surrounding the heat exchanger. The actual data of the heat exchanger's environment can include, but is not limited to, the actual temperature and humidity of the environment surrounding the heat exchanger. The actual data of the coolant in the heat exchanger can be obtained through actual monitoring, and include status data of the coolant in the heat exchanger; the status data can include, but is not limited to, temperature, flow rate, and pressure.

[0083] Specifically, a certain algorithm is used to perform fault detection on the heat exchanger based on standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, standard data of the coolant of the heat exchanger, actual data of the coolant of the heat exchanger, actual data of the coolant of the main circulation pump, specific heat capacity of the coolant and the maximum heat transfer rate of the heat exchanger, to obtain a fault detection result of the heat exchanger; if the fault detection result of the heat exchanger is normal and the fault detection result of the nuclear power plant cooling system is normal, then the final detection result of the nuclear power plant cooling system is determined to be normal; otherwise, the final detection result of the nuclear power plant cooling system is determined to be abnormal.

[0084] Optionally, the actual coolant data of the heat exchanger includes the actual coolant flow rate at the heat exchanger input end, the actual coolant flow rate at the heat exchanger output end, the actual coolant temperature at the heat exchanger input end, and the actual coolant temperature at the heat exchanger output end; the actual coolant data of the main circulation pump includes the actual coolant temperature at the main circulation pump output end; the coolant standard data of the heat exchanger includes the coolant set temperature at the heat exchanger output end;

[0085] Based on the standard data of the environment in which the heat exchanger is located, the actual data of the environment in which the heat exchanger is located, the standard data of the coolant in the heat exchanger, the actual data of the coolant in the heat exchanger, the actual data of the coolant in the main circulation pump, the specific heat capacity of the coolant and the maximum heat transfer rate of the heat exchanger, the heat exchanger fault detection is performed to obtain the fault detection results of the heat exchanger, including:

[0086] The average coolant flow rate of the heat exchanger is determined based on the actual coolant flow rate at the input end of the heat exchanger and the actual coolant flow rate at the output end of the heat exchanger; the actual heat transfer rate of the heat exchanger is determined based on the average coolant flow rate, the specific heat capacity of the coolant, the actual coolant temperature at the output end of the heat exchanger and the actual coolant temperature at the output end of the main circulation pump; the heat exchanger is fault detected based on the actual heat transfer rate of the heat exchanger, standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, the actual coolant temperature at the output end of the heat exchanger, the specific heat capacity of the coolant, the actual heat transfer rate of the heat exchanger and the maximum heat transfer rate of the heat exchanger to obtain a fault detection result of the heat exchanger.

[0087] The heat exchanger input end may be the end of the heat exchanger where coolant is input; the heat exchanger output end may be the end where coolant is output. The actual coolant flow rate at the heat exchanger input end may be the coolant flow rate at the heat exchanger input end obtained by actual monitoring; the actual coolant flow rate at the heat exchanger output end may be the coolant flow rate at the heat exchanger output end obtained by actual monitoring; the actual coolant temperature at the heat exchanger input end may be the coolant temperature at the heat exchanger output end obtained by actual monitoring; the actual coolant temperature at the heat exchanger output end may be the coolant temperature at the heat exchanger output end obtained by actual monitoring; the coolant set temperature at the heat exchanger output end may be the coolant temperature at the heat exchanger output end set by a technician under fault-free cooling conditions of a nuclear power plant. The actual heat transfer rate of the heat exchanger may be the actual heat transfer rate of the heat exchanger.

[0088] Specifically, the average of the actual coolant flow rate at the heat exchanger input end and the actual coolant flow rate at the heat exchanger output end is determined as the average coolant flow rate of the heat exchanger. Exemplarily, the average coolant flow rate of the heat exchanger can be expressed by the following formula:

[0089]

[0090] Where m represents the average coolant flow rate of the heat exchanger; l in is the actual flow rate of coolant at the input end of the heat exchanger, l out is the actual coolant flow at the output end of the heat exchanger.

[0091] Determine the absolute value of the temperature difference between the actual coolant temperature at the output end of the heat exchanger and the set coolant temperature at the output end of the heat exchanger; determine the actual heat transfer rate of the heat exchanger based on the average coolant flow rate, the specific heat capacity of the coolant, and the absolute value of the temperature difference between the actual coolant temperature at the output end of the heat exchanger and the set coolant temperature at the output end of the heat exchanger; illustratively, the actual heat transfer rate of the heat exchanger can be determined by the following formula:

[0092] q s =m×c×|Temp s -Tout s |;

[0093] Among them, q s represents the actual heat transfer rate of the heat exchanger; m is the average flow rate of the coolant; c is the specific heat capacity of the coolant; Temp s is the actual temperature of the coolant at the output end of the heat exchanger; Tout s Indicates the actual coolant temperature at the output of the main circulation pump.

[0094] A certain algorithm is used to perform fault detection on the heat exchanger based on the actual heat transfer rate of the heat exchanger, standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, the actual temperature of the coolant at the output end of the heat exchanger, the specific heat capacity of the coolant, the actual heat transfer rate of the heat exchanger and the maximum heat transfer rate of the heat exchanger, and obtain a fault detection result of the heat exchanger.

[0095] It can be understood that by adopting the above technical solution, the actual flow rate of the coolant and the actual heat transfer rate of the heat exchanger can be determined, and then based on the data characterizing the working status of the heat exchanger at different latitudes such as the actual heat transfer rate of the heat exchanger, the standard data of the environment in which the heat exchanger is located, the actual data of the environment in which the heat exchanger is located, the actual temperature of the coolant at the output end of the heat exchanger, the specific heat capacity of the coolant, the actual heat transfer rate of the heat exchanger and the maximum heat transfer rate of the heat exchanger, the heat exchanger can be comprehensively and comprehensively detected for faults, thereby improving the accuracy of the fault detection results of the heat exchanger.

[0096] Optionally, a fault detection is performed on the heat exchanger based on an actual heat transfer rate of the heat exchanger, standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, an actual temperature of the coolant at the output end of the heat exchanger, a specific heat capacity of the coolant, an actual heat transfer rate of the heat exchanger, and a maximum heat transfer rate of the heat exchanger, to obtain a fault detection result of the heat exchanger, including:

[0097] The temperature deviation index value of the heat exchanger is determined based on the actual temperature of the coolant at the output end of the heat exchanger and the set temperature of the coolant at the input end of the heat exchanger; the heat transfer deviation index value of the heat exchanger is determined based on the actual heat transfer rate of the heat exchanger and the maximum heat transfer rate of the heat exchanger; the environmental abnormality index value of the heat exchanger is determined based on the standard data of the environment in which the heat exchanger is located and the actual data of the heat exchanger environment; based on the temperature deviation index value of the heat exchanger, the heat transfer deviation index value of the heat exchanger and the environmental abnormality index value of the heat exchanger, the heat exchanger is fault detected to obtain the fault detection result of the heat exchanger.

[0098] Among them, the temperature deviation index value of the heat exchanger can be used to characterize the degree to which the actual temperature of the coolant at the output end of the heat exchanger deviates from the set temperature of the coolant at the output end of the heat exchanger; the heat transfer deviation index value of the heat exchanger can be used to characterize the degree to which the actual heat transfer rate of the heat exchanger deviates from the maximum heat transfer rate of the heat exchanger; the environmental abnormality index value of the heat exchanger can be used to characterize the degree to which the actual data of the environment in which the heat exchanger is located deviates from the standard data of the environment in which the heat exchanger is located.

[0099] Specifically, the absolute value of the temperature difference between the actual temperature of the coolant at the output end of the heat exchanger and the set temperature of the coolant at the input end of the heat exchanger is determined as the temperature deviation index value of the heat exchanger; the ratio of the actual heat transfer rate of the heat exchanger to the maximum heat transfer rate of the heat exchanger is determined as the heat transfer deviation index value of the heat exchanger; the environmental abnormality index value of the heat exchanger is determined based on the standard data of the environment in which the heat exchanger is located and the actual data of the heat exchanger environment; the fault index value of the heat exchanger is determined based on the temperature deviation index value of the heat exchanger, the heat transfer deviation index value of the heat exchanger and the environmental abnormality index value of the heat exchanger; the fault index value of the heat exchanger can be used as an indicator to measure whether the heat exchanger of a nuclear power plant is normal, that is, an indicator value of whether it is operating safely.

[0100] For example, the failure index value of the heat exchanger may be determined by the following formula:

[0101]

[0102] Among them, Q he Indicates the fault index value of the heat exchanger; q s Indicates the actual heat transfer rate of the heat exchanger; q max Indicates the maximum heat transfer rate of the heat exchanger; Temp s Indicates the actual temperature of the coolant at the output end of the heat exchanger; Temp r Indicates the coolant set temperature at the heat exchanger output end; w s Indicates the actual temperature of the environment where the heat exchanger is located; w r Indicates the set temperature of the environment where the heat exchanger is located; s s Indicates the actual humidity of the environment where the heat exchanger is located; r Indicates the set humidity of the environment where the heat exchanger is located;

[0103] For the fault index value of the heat exchanger and the fault index threshold of the heat exchanger; if the fault index value of the heat exchanger is greater than or equal to the fault index threshold of the heat exchanger, the fault detection result of the heat exchanger is determined to be a fault; if the fault index value of the heat exchanger is less than the fault index threshold of the heat exchanger, the fault detection result of the heat exchanger is determined to be normal.

[0104] It can be understood that by adopting the above technical solution, the temperature deviation index value, heat transfer deviation index value and environmental deviation index value of the heat exchanger are determined respectively, and then the fault index value of the heat exchanger is comprehensively and comprehensively determined through data of different dimensions, thereby improving the accuracy of the fault detection results of the heat exchanger.

[0105] The technical solution of the embodiment of the present invention not only performs fault detection on the main circulation pipeline, but also performs fault detection on the heat exchanger in the cooling system. It determines whether the nuclear power plant cooling system has a fault based on the fault detection result of the heat exchanger and the fault detection result of the nuclear power plant cooling system determined based on the main circulation pipeline. This can avoid the situation where the cooling system fault is not detected when the main circulation pipeline is normal but the heat exchanger is faulty, thereby improving the accuracy of fault detection of the nuclear power plant cooling system.

[0106] Example 4

[0107] Figure 4 This is a schematic diagram of the structure of a nuclear power plant cooling system fault detection device provided in Embodiment 4 of the present invention. This embodiment of the present invention is applicable to situations where fault detection is performed on a nuclear power plant cooling system. The device can execute a method for detecting a fault in a nuclear power plant cooling system. The device can be implemented in hardware and / or software and can be configured in a nuclear power plant cooling system fault detection device, such as a server.

[0108] See also Figure 4 The fault detection device for the cooling system of a nuclear power plant shown in the figure includes a data acquisition module 401, a data monitoring module 402, a pipeline detection module 403 and a cooling system detection module 404, wherein:

[0109] The data acquisition module 401 is used to obtain the coolant standard data of the main circulation pump in the cooling system of the nuclear power plant;

[0110] The data monitoring module 402 is used to monitor the actual data of the coolant of the main circulation pump;

[0111] The pipeline detection module 403 is used to perform fault detection on the main circulation pipeline in the nuclear power plant cooling system based on the coolant standard data and the coolant actual data of the main circulation pump, and obtain the detection result of the main circulation pipeline in the nuclear power plant cooling system;

[0112] The cooling system detection module 404 is used to determine the fault detection result of the nuclear power plant cooling system according to the detection result of the main circulation pipeline.

[0113] The embodiment of the present invention obtains the coolant standard data of the main circulation pump in the nuclear power plant cooling system through the data acquisition module; monitors the actual coolant data of the main circulation pump through the data monitoring module; performs fault detection on the main circulation pipeline in the nuclear power plant cooling system according to the coolant standard data of the main circulation pump and the actual coolant data of the main circulation pump through the pipeline detection module, and obtains the detection result of the main circulation pipeline in the nuclear power plant cooling system; determines the fault detection result of the nuclear power plant cooling system according to the detection result of the main circulation pipeline through the cooling system detection module. Compared with the solution of manually judging the working condition of the cooling system in the prior art, the present technical solution realizes the automatic fault detection of the nuclear power plant cooling system, improves the accuracy and efficiency of the fault detection of the nuclear power plant cooling system; through the automatic cooling system fault detection, it is possible to detect and prevent possible safety problems of the nuclear power plant in time, thereby improving the safety and operational reliability of the nuclear power plant.

[0114] Optionally, in the device, the standard data of the coolant of the main circulation pump include: the set temperature of the coolant at the output end of the main circulation pump, the set flow rate of the coolant at the output end of the main circulation pump, and the set pressure of the coolant at the output end of the main circulation pump; the actual data of the coolant of the main circulation pump include: the actual temperature of the coolant at the output end of the main circulation pump, the actual flow rate of the coolant at the output end of the main circulation pump, and the actual pressure of the coolant at the output end of the main circulation pump.

[0115] Optionally, the pipeline detection module 403 includes:

[0116] a fault indicator value determining unit, configured to determine a fault indicator value of the main circulation pipeline according to a set coolant temperature at an output end of the main circulation pump, a set coolant flow rate at an output end of the main circulation pump, a set coolant pressure at an output end of the main circulation pump, an actual coolant temperature at an output end of the main circulation pump, an actual coolant flow rate at an output end of the main circulation pump, and an actual coolant pressure at an output end of the main circulation pump;

[0117] The pipeline detection unit is used to perform fault detection on the main circulation pipeline according to the fault index value of the main circulation pipeline and the fault index threshold of the main circulation pipeline, and determine the detection result of the main circulation pipeline.

[0118] Optionally, the fault indicator value determination unit is specifically configured to:

[0119] According to the coolant set temperature and the actual coolant temperature at the output end of the main circulation pump, the main circulation pipeline is tested for temperature faults to obtain a temperature deviation index value of the main circulation pipeline;

[0120] According to the set flow rate of the coolant at the output end of the main circulation pump and the actual flow rate of the coolant at the output end of the main circulation pump, a flow rate fault detection is performed on the main circulation pipeline to obtain a flow rate deviation index value of the main circulation pipeline;

[0121] According to the coolant set pressure at the output end of the main circulation pump and the actual coolant pressure at the output end of the main circulation pump, a pressure fault detection is performed on the main circulation pipeline to obtain a pressure deviation index value of the main circulation pipeline;

[0122] The fault index value of the main circulation pipeline is determined according to the temperature deviation index value of the main circulation pipeline, the flow velocity deviation index value of the main circulation pipeline, and the pressure deviation index value of the main circulation pipeline.

[0123] Optionally, the device further includes:

[0124] The heat exchanger data acquisition module is used to obtain the standard data of the environment in which the heat exchanger is located and the standard data of the coolant of the heat exchanger in the nuclear power plant cooling system;

[0125] A heat exchanger data monitoring module is used to monitor the actual data of the environment in which the heat exchanger is located and the actual data of the coolant in the heat exchanger;

[0126] A heat exchanger detection module is used to perform fault detection on the heat exchanger based on standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, standard data of the coolant in the heat exchanger, actual data of the coolant in the heat exchanger, actual data of the coolant in the main circulation pump, specific heat capacity of the coolant, and maximum heat transfer rate of the heat exchanger, and obtain a fault detection result of the heat exchanger;

[0127] The final result determination module is used to determine the final detection result of the nuclear power plant cooling system according to the fault detection result of the heat exchanger and the fault detection result of the nuclear power plant cooling system.

[0128] Optionally, in the device, the actual coolant data of the heat exchanger includes the actual coolant flow rate at the heat exchanger input end, the actual coolant flow rate at the heat exchanger output end, the actual coolant temperature at the heat exchanger input end, and the actual coolant temperature at the heat exchanger output end; the actual coolant data of the main circulation pump includes the actual coolant temperature at the main circulation pump output end; the coolant standard data of the heat exchanger includes the coolant set temperature at the heat exchanger output end;

[0129] Heat exchanger detection module, including:

[0130] a flow determination unit, configured to determine an average flow rate of the coolant of the heat exchanger based on an actual flow rate of the coolant at an input end of the heat exchanger and an actual flow rate of the coolant at an output end of the heat exchanger;

[0131] a heat transfer rate determination unit, configured to determine an actual heat transfer rate of the heat exchanger based on an average coolant flow rate, a specific heat capacity of the coolant, an actual coolant temperature at an output end of the heat exchanger, and an actual coolant temperature at an output end of a main circulation pump;

[0132] The heat exchanger detection unit is used to perform fault detection on the heat exchanger based on the actual heat transfer rate of the heat exchanger, standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, the actual temperature of the coolant at the output end of the heat exchanger, the specific heat capacity of the coolant, the actual heat transfer rate of the heat exchanger and the maximum heat transfer rate of the heat exchanger, and obtain a fault detection result of the heat exchanger.

[0133] Optional heat exchanger detection unit, specifically used for:

[0134] Determining a temperature deviation index value of the heat exchanger based on the actual coolant temperature at the output end of the heat exchanger and the set coolant temperature at the input end of the heat exchanger;

[0135] Determine the heat transfer deviation index value of the heat exchanger based on the actual heat transfer rate of the heat exchanger and the maximum heat transfer rate of the heat exchanger;

[0136] Determine the environmental abnormality index value of the heat exchanger based on the standard data of the environment in which the heat exchanger is located and the actual data of the heat exchanger environment;

[0137] According to the temperature deviation index value of the heat exchanger, the heat transfer deviation index value of the heat exchanger and the environmental abnormality index value of the heat exchanger, a fault detection is performed on the heat exchanger to obtain a fault detection result of the heat exchanger.

[0138] Optionally, the device further includes:

[0139] The communication module is used to send fault detection results of the nuclear power plant cooling system to technicians.

[0140] The fault detection device for a nuclear power plant cooling system provided in an embodiment of the present invention can execute the fault detection method for a nuclear power plant cooling system provided in any embodiment of the present invention, and has corresponding functional modules and beneficial effects for executing the fault detection method for a nuclear power plant cooling system.

[0141] Example 5

[0142] Figure 5The structural diagram of the fault detection device 500 of the nuclear power plant cooling system that can be used to implement an embodiment of the present invention is shown. The fault detection device of the nuclear power plant cooling system is intended to represent various forms of digital computers, such as laptop computers, desktop computers, workstations, personal digital assistants, servers, blade servers, mainframe computers, and other suitable computers. The fault detection device of the nuclear power plant cooling system can also represent various forms of mobile devices, such as personal digital processing, cellular phones, smart phones, wearable devices (such as helmets, glasses, watches, etc.) and other similar computing devices. The components shown herein, their connections and relationships, and their functions are merely examples and are not intended to limit the implementation of the present invention described and / or required herein.

[0143] like Figure 5 As shown, a fault detection device 500 for a nuclear power plant cooling system includes at least one processor 501 and a memory, such as a read-only memory (ROM) 502 or a random access memory (RAM) 503, communicatively connected to the at least one processor 501. The memory stores a computer program executable by the at least one processor. The processor 501 can perform various appropriate actions and processes based on the computer program stored in the read-only memory (ROM) 502 or loaded from a storage unit 508 into the random access memory (RAM) 503. RAM 503 can also store various programs and data required for the operation of the fault detection device 500 for a nuclear power plant cooling system. The processor 501, ROM 502, and RAM 503 are interconnected via a bus 504. An input / output (I / O) interface 505 is also connected to the bus 504.

[0144] Multiple components in the nuclear power plant cooling system fault detection device 500 are connected to an I / O interface 505, including: an input unit 506, such as a keyboard, mouse, etc.; an output unit 507, such as various types of displays, speakers, etc.; a storage unit 508, such as a magnetic disk, optical disk, etc.; and a communication unit 509, such as a network card, modem, wireless communication transceiver, etc. The communication unit 509 allows the nuclear power plant cooling system fault detection device 500 to exchange information / data with other devices via a computer network such as the Internet and / or various telecommunication networks.

[0145] The processor 501 can be any general-purpose and / or specialized processing component with processing and computing capabilities. Some examples of the processor 501 include, but are not limited to, a central processing unit (CPU), a graphics processing unit (GPU), various specialized artificial intelligence (AI) computing chips, various processors running machine learning model algorithms, a digital signal processor (DSP), and any appropriate processor, controller, microcontroller, etc. The processor 501 executes the various methods and processes described above, such as a fault detection method for a nuclear power plant cooling system.

[0146] In some embodiments, the fault detection method for a nuclear power plant cooling system may be implemented as a computer program, which is tangibly contained in a computer-readable storage medium, such as a storage unit 508. In some embodiments, part or all of the computer program may be loaded and / or installed on the fault detection device 500 for a nuclear power plant cooling system via the ROM 502 and / or the communication unit 509. When the computer program is loaded into the RAM 503 and executed by the processor 501, one or more steps of the fault detection method for a nuclear power plant cooling system described above may be performed. Alternatively, in other embodiments, the processor 501 may be configured to execute the fault detection method for a nuclear power plant cooling system in any other appropriate manner (e.g., by means of firmware).

[0147] Various embodiments of the systems and techniques described above can be implemented in digital electronic circuit systems, integrated circuit systems, field programmable gate arrays (FPGAs), application specific integrated circuits (ASICs), application specific standard products (ASSPs), system-on-chip systems (SOCs), complex programmable logic devices (CPLDs), computer hardware, firmware, software, and / or combinations thereof. These various embodiments can include being implemented in one or more computer programs that are executable and / or interpreted on a programmable system that includes at least one programmable processor, which can be a special purpose or general purpose programmable processor that can receive data and instructions from a storage system, at least one input device, and at least one output device, and transmit data and instructions to the storage system, the at least one input device, and the at least one output device.

[0148] Computer programs for implementing the methods of the present invention can be written in any combination of one or more programming languages. These computer programs can be provided to a processor of a general-purpose computer, a special-purpose computer, or other programmable nuclear power plant cooling system fault detection device, so that when executed by the processor, the computer programs implement the functions / operations specified in the flowcharts and / or block diagrams. The computer programs can be executed entirely on the machine, partially on the machine, as a stand-alone software package, partially on the machine and partially on a remote machine, or entirely on a remote machine or server.

[0149] In the context of the present invention, computer-readable storage media can be tangible media that can contain or store a computer program for use with an instruction execution system, device or equipment or used in combination with an instruction execution system, device or equipment. Computer-readable storage media can include but are not limited to electronic, magnetic, optical, electromagnetic, infrared or semiconductor systems, devices or equipment, or any suitable combination of the foregoing. Alternatively, computer-readable storage media can be machine-readable signal media. More specific examples of machine-readable storage media can include electrical connections based on one or more lines, portable computer disks, hard disks, random access memories (RAM), read-only memories (ROM), erasable programmable read-only memories (EPROM or flash memory), optical fibers, portable compact disk read-only memories (CD-ROM), optical storage devices, magnetic storage devices, or any suitable combination of the foregoing.

[0150] To provide interaction with a user, the systems and techniques described herein can be implemented on a fault detection device for a nuclear power plant cooling system, which has: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to a user; and a keyboard and a pointing device (e.g., a mouse or trackball), through which a user can provide input to the fault detection device for a nuclear power plant cooling system. Other types of devices can also be used to provide interaction with a user; for example, the feedback provided to the user can be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user can be received in any form (including acoustic input, voice input, or tactile input).

[0151] The systems and techniques described herein can be implemented in a computing system that includes back-end components (e.g., as a data server), or a computing system that includes middleware components (e.g., an application server), or a computing system that includes front-end components (e.g., a user computer with a graphical user interface or web browser through which a user can interact with implementations of the systems and techniques described herein), or a computing system that includes any combination of such back-end components, middleware components, or front-end components. The components of the system can be interconnected by any form or medium of digital data communication (e.g., a communication network). Examples of communication networks include: a local area network (LAN), a wide area network (WAN), a blockchain network, and the Internet.

[0152] A computing system may include clients and servers. The clients and servers are generally remote from each other and typically interact via a communication network. This client-server relationship arises through computer programs running on the respective computers, creating a client-server relationship. The server may be a cloud server, also known as a cloud computing server or cloud host. This server is a hosting product within a cloud computing service ecosystem that addresses the management difficulties and limited scalability of traditional physical hosting and VPS (Virtual Private Server) services.

[0153] It should be understood that the various forms of the processes shown above can be used to reorder, add, or delete steps. For example, the steps described in the present invention can be performed in parallel, sequentially, or in a different order, as long as the desired results of the technical solution of the present invention can be achieved. This is not limited herein.

[0154] The above specific embodiments do not limit the scope of protection of the present invention. Those skilled in the art will appreciate that various modifications, combinations, sub-combinations, and substitutions may be made based on design requirements and other factors. Any modifications, equivalent substitutions, and improvements made within the spirit and principles of the present invention are intended to be included within the scope of protection of the present invention.

Claims

1. A method for detecting a fault in a cooling system of a nuclear power plant, characterized in that: The method comprises: Obtain coolant standard data for the main circulation pump in the nuclear power plant cooling system; Monitoring actual coolant data of the main circulation pump; performing fault detection on the main circulation pipeline in the cooling system of the nuclear power plant according to the coolant standard data of the main circulation pump and the coolant actual data of the main circulation pump, and obtaining a detection result of the main circulation pipeline in the cooling system of the nuclear power plant; The fault detection result of the nuclear power plant cooling system is determined based on the detection result of the main circulation pipeline.

2. The method according to claim 1, characterized in that The standard data of the coolant of the main circulation pump include: the set temperature of the coolant at the output end of the main circulation pump, the set flow rate of the coolant at the output end of the main circulation pump, and the set pressure of the coolant at the output end of the main circulation pump; the actual data of the coolant of the main circulation pump include: the actual temperature of the coolant at the output end of the main circulation pump, the actual flow rate of the coolant at the output end of the main circulation pump, and the actual pressure of the coolant at the output end of the main circulation pump.

3. The method according to claim 2, characterized in that The method of performing fault detection on the main circulation pipeline in the cooling system of the nuclear power plant according to the coolant standard data of the main circulation pump and the coolant actual data of the main circulation pump to obtain the detection result of the main circulation pipeline in the cooling system of the nuclear power plant includes: Determine a fault index value of the main circulation pipeline according to the coolant set temperature at the output end of the main circulation pump, the coolant set flow rate at the output end of the main circulation pump, the coolant set pressure at the output end of the main circulation pump, the coolant actual temperature at the output end of the main circulation pump, the coolant actual flow rate at the output end of the main circulation pump, and the coolant actual pressure at the output end of the main circulation pump; According to the fault index value of the main circulation pipeline and the fault index threshold value of the main circulation pipeline, fault detection is performed on the main circulation pipeline to determine the detection result of the main circulation pipeline.

4. The method according to claim 3, characterized in that Determining the fault index value of the main circulation pipeline according to the coolant set temperature at the output end of the main circulation pump, the coolant set flow rate at the output end of the main circulation pump, the coolant set pressure at the output end of the main circulation pump, the coolant actual temperature at the output end of the main circulation pump, the coolant actual flow rate at the output end of the main circulation pump, and the coolant actual pressure at the output end of the main circulation pump includes: performing temperature fault detection on the main circulation pipeline according to the coolant set temperature at the output end of the main circulation pump and the actual temperature of the coolant at the output end of the main circulation pump to obtain a temperature deviation index value of the main circulation pipeline; performing flow rate fault detection on the main circulation pipeline according to the set flow rate of the coolant at the output end of the main circulation pump and the actual flow rate of the coolant at the output end of the main circulation pump to obtain a flow rate deviation index value of the main circulation pipeline; performing pressure fault detection on the main circulation pipeline according to the coolant set pressure at the output end of the main circulation pump and the actual coolant pressure at the output end of the main circulation pump to obtain a pressure deviation index value of the main circulation pipeline; A fault index value of the main circulation pipeline is determined according to a temperature deviation index value of the main circulation pipeline, a flow velocity deviation index value of the main circulation pipeline, and a pressure deviation index value of the main circulation pipeline.

5. The method according to claim 1, wherein The method further comprises: Obtaining standard data of the environment in which the heat exchanger is located and standard data of the coolant of the heat exchanger in the cooling system of the nuclear power plant; Monitoring actual data of the environment in which the heat exchanger is located and actual data of the coolant in the heat exchanger; performing fault detection on the heat exchanger based on standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, standard data of the coolant in the heat exchanger, actual data of the coolant in the heat exchanger, actual data of the coolant in the main circulation pump, specific heat capacity of the coolant, and maximum heat transfer rate of the heat exchanger to obtain a fault detection result of the heat exchanger; The final detection result of the nuclear power plant cooling system is determined according to the fault detection result of the heat exchanger and the fault detection result of the nuclear power plant cooling system.

6. The method according to claim 5, characterized in that The actual coolant data of the heat exchanger includes the actual coolant flow rate at the heat exchanger input end, the actual coolant flow rate at the heat exchanger output end, the actual coolant temperature at the heat exchanger input end, and the actual coolant temperature at the heat exchanger output end; The actual coolant data of the main circulation pump includes the actual coolant temperature at the output end of the main circulation pump; the standard coolant data of the heat exchanger includes the set coolant temperature at the output end of the heat exchanger; The method of performing fault detection on the heat exchanger based on standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, standard data of the coolant in the heat exchanger, actual data of the coolant in the heat exchanger, actual data of the coolant in the main circulation pump, specific heat capacity of the coolant, and maximum heat transfer rate of the heat exchanger to obtain a fault detection result of the heat exchanger includes: determining an average coolant flow rate of the heat exchanger according to an actual coolant flow rate at an input end of the heat exchanger and an actual coolant flow rate at an output end of the heat exchanger; determining an actual heat transfer rate of the heat exchanger based on the average flow rate of the coolant, the specific heat capacity of the coolant, the actual temperature of the coolant at the output end of the heat exchanger, and the actual temperature of the coolant at the output end of the main circulation pump; Based on the actual heat transfer rate of the heat exchanger, standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, the actual temperature of the coolant at the output end of the heat exchanger, the specific heat capacity of the coolant, the actual heat transfer rate of the heat exchanger and the maximum heat transfer rate of the heat exchanger, the heat exchanger is fault detected to obtain a fault detection result of the heat exchanger.

7. The method according to claim 6, characterized in that The heat exchanger is subjected to fault detection based on the actual heat transfer rate of the heat exchanger, standard data of the environment in which the heat exchanger is located, actual data of the environment in which the heat exchanger is located, the actual temperature of the coolant at the output end of the heat exchanger, the specific heat capacity of the coolant, the actual heat transfer rate of the heat exchanger, and the maximum heat transfer rate of the heat exchanger to obtain a fault detection result of the heat exchanger, including: determining a temperature deviation index value of the heat exchanger according to an actual coolant temperature at an output end of the heat exchanger and a set coolant temperature at an input end of the heat exchanger; determining a heat transfer deviation index value of the heat exchanger according to an actual heat transfer rate of the heat exchanger and a maximum heat transfer rate of the heat exchanger; Determining an environmental abnormality index value of the heat exchanger according to standard data of the environment in which the heat exchanger is located and actual data of the environment of the heat exchanger; The heat exchanger is subjected to fault detection according to the temperature deviation index value of the heat exchanger, the heat transfer deviation index value of the heat exchanger and the environmental abnormality index value of the heat exchanger to obtain a fault detection result of the heat exchanger.

8. A fault detection system for a nuclear power plant cooling system, characterized in that: The system comprises: A data acquisition module is used to obtain coolant standard data of the main circulation pump in the cooling system of the nuclear power plant; A data monitoring module, used for monitoring actual coolant data of the main circulation pump; a pipeline detection module, configured to perform fault detection on the main circulation pipeline in the cooling system of the nuclear power plant according to the coolant standard data of the main circulation pump and the coolant actual data of the main circulation pump, and obtain a detection result of the main circulation pipeline in the cooling system of the nuclear power plant; The cooling system detection module is used to determine the fault detection result of the nuclear power plant cooling system according to the detection result of the main circulation pipeline.

9. An electronic device, characterized in that: The device comprises: at least one processor; and a memory communicatively connected to the at least one processor; wherein, The memory stores a computer program executable by the at least one processor, and the computer program is executed by the at least one processor to enable the at least one processor to perform the method according to any one of claims 1 to 7.

10. A computer-readable storage medium, characterized in that The computer-readable storage medium stores computer instructions, and the computer instructions are used to enable a processor to implement the fault detection method for a nuclear power plant cooling system according to any one of claims 1 to 7 when executed.

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