Method and device for determining real-time leakage rate of nuclear power plant main system

Abstract

The present disclosure belongs to the field of nuclear power technology, and specifically relates to a method and apparatus for determining the real-time leakage rate of a nuclear power plant's main system. The disclosed method for determining the real-time leakage rate of a nuclear power plant's main system determines the leakage rate of the nuclear power plant's main system during a detection period based on changes in the liquid level of the control box, the liquid level of the pressurizer, and the temperature of the primary circuit. Main system parameters can be collected in real time and the leakage rate of the main system calculated, thereby enabling timely and accurate monitoring of leakage in the main system, avoiding human error and reducing human radiation exposure. This method has been successfully used to monitor the real-time leakage rate of the main system of nuclear power plant units.

Description

Technical Field

[0001] The present invention belongs to the technical field of nuclear power, and in particular relates to a method and device for determining the real-time leakage rate of a main system of a nuclear power plant. Background Art

[0002] The primary circuit of a nuclear power plant is a crucial system for transferring energy from the core to the secondary circuit. If the primary system's coolant leaks, resulting in insufficient coolant, could severely damage the core. Therefore, inspectors are required to monitor the leakage rate of the primary system. The current method involves inspectors performing periodic tests to calculate a leakage rate, which they then use to monitor changes in the primary system's leakage rate and maintain the stability of the primary circuit. However, this method results in large errors and fluctuations in the calculated results. Summary of the Invention

[0003] In order to overcome the problems existing in the related art, a method and device for determining the real-time leakage rate of the main system of a nuclear power plant are provided.

[0004] According to one aspect of an embodiment of the present disclosure, a method for determining a real-time leakage rate of a main system of a nuclear power plant is provided, the method comprising:

[0005] Step 10, obtaining the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the beginning of the detection period, and obtaining the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the end of the detection period;

[0006] Step 11: Determine the leakage rate of the nuclear power plant main system during the detection period based on the liquid level changes of the control box, the liquid level changes of the pressurizer, and the temperature changes of the primary circuit during the detection period.

[0007] In one possible implementation, step 11 includes:

[0008] Step 110: Determine the leakage rate Fp of the nuclear power plant main system during the detection period according to Formula 1:

[0009]

[0010] Among them, N1 is the liquid level of the control tank at the first time point, N3 is the liquid level of the pressurizer at the first time point, T1 is the average temperature of the primary circuit at the first time point, N2 is the liquid level of the control tank at the second time point, N4 is the liquid level of the pressurizer at the second time point, T2 is the average temperature of the primary circuit at the second time point, and Δt is the time from the first time point to the second time point.

[0011] It should be noted that different weighting values ​​can be selected for the control tank level change (N1-N2) / Δt, the pressurizer level change (N3-N4) / Δt, and the primary circuit temperature change (T1-T2) / Δt as needed.

[0012] In a possible implementation, the method further includes:

[0013] Step 12: If it is detected that the control box drains water from the TEP header tank and / or replenishes water and boron from the control box during the detection period, the cumulative duration Δt' of the control box draining water from the TEP header tank and / or replenishing water and boron from the control box during the detection period, the liquid level change ΔN1 caused by the control box draining water from the TEP header tank, and the liquid level change ΔN2 caused by the control box replenishing water and boron;

[0014] The step 11 further includes: step 111, determining the leakage rate Fp of the nuclear power plant main system during the detection period according to formula 2:

[0015]

[0016] Among them, Δt' is the cumulative duration of the content control box draining water to the TEP header box and / or replenishing water and boron in the control box during the detection period, ΔN1 is the absolute value of the liquid level change caused by the content control box draining water to the TEP header box during the detection period, and ΔN2 is the absolute value of the liquid level change caused by the content control box replenishing water and boron in the detection period.

[0017] In a possible implementation, the method further includes:

[0018] Step 13: Set multiple detection periods for the main system of the nuclear power plant, and for each of the multiple detection periods, use the methods of steps 10 and 11 to obtain the leakage rate of the main system of the nuclear power plant during the detection period.

[0019] According to another aspect of an embodiment of the present disclosure, a device for determining a real-time leakage rate of a main system of a nuclear power plant is provided, the device comprising:

[0020] a first acquisition module, configured to acquire the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the beginning of a detection period, and to acquire the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the end of the detection period;

[0021] The determination module is used to determine the leakage rate of the nuclear power plant main system during the detection period based on the liquid level changes of the control box during the detection period, the liquid level changes of the regulator during the detection period, and the temperature changes of the primary circuit during the detection period.

[0022] In a possible implementation, the determining module includes:

[0023] The first determination submodule is used to determine the leakage rate Fp of the nuclear power plant main system during the detection period according to Formula 1:

[0024]

[0025] Among them, N1 is the liquid level of the control tank at the first time point, N3 is the liquid level of the pressurizer at the first time point, T1 is the average temperature of the primary circuit at the first time point, N2 is the liquid level of the control tank at the second time point, N4 is the liquid level of the pressurizer at the second time point, T2 is the average temperature of the primary circuit at the second time point, and Δt is the time from the first time point to the second time point.

[0026] In a possible implementation, the apparatus further includes:

[0027] The second acquisition module is used to obtain, when it is detected that the control box drains water from the TEP header box and / or replenishes water and boron in the control box within the detection period, the cumulative duration Δt' of the control box draining water from the TEP header box and / or replenishing water and boron in the control box during the detection period, the liquid level change ΔN1 caused by the control box draining water from the TEP header box, and the liquid level change ΔN2 caused by the control box replenishing water and boron;

[0028] The determination module further includes: a second determination submodule, configured to determine the leakage rate Fp of the nuclear power plant main system during the detection period according to Formula 2:

[0029]

[0030] Among them, Δt' is the cumulative duration of the content control box draining water to the TEP header box and / or replenishing water and boron in the control box during the detection period, ΔN1 is the absolute value of the liquid level change caused by the content control box draining water to the TEP header box during the detection period, and ΔN2 is the absolute value of the liquid level change caused by the content control box replenishing water and boron in the detection period.

[0031] In a possible implementation, the apparatus further includes:

[0032] The overall detection module is used to set multiple detection periods for the main system of the nuclear power plant, and for each detection period in the multiple periods, use the first acquisition module and the determination module to determine the leakage rate of the main system of the nuclear power plant in the detection period.

[0033] According to another aspect of an embodiment of the present disclosure, a device for determining a real-time leakage rate of a main system of a nuclear power plant is provided, the device comprising:

[0034] processor;

[0035] a memory for storing processor-executable instructions;

[0036] The processor is configured to execute the above method.

[0037] According to another aspect of an embodiment of the present disclosure, a non-volatile computer-readable storage medium is provided, on which computer program instructions are stored. When the computer program instructions are executed by a processor, the above method is implemented.

[0038] The beneficial effects of this disclosure lie in the following: The disclosed method for determining the real-time leakage rate of a nuclear power plant's main system determines the leakage rate of the nuclear power plant's main system during a detection period based on the changes in the liquid level of the control box, the liquid level of the pressurizer, and the temperature of the primary circuit during the detection period. This method collects main system parameters in real time and calculates the leakage rate of the main system, thereby enabling timely and accurate monitoring of main system leakage, avoiding human error and reducing personnel radiation exposure. This method has been successfully used to monitor the real-time leakage rate of the main system of nuclear power plant units. BRIEF DESCRIPTION OF THE DRAWINGS

[0039] Figure 1 is a schematic diagram showing a real-time leakage rate according to an exemplary embodiment.

[0040] Figure 2 The present invention is a block diagram showing a device for determining a real-time leakage rate of a main system of a nuclear power plant according to an exemplary embodiment.

[0041] Figure 3 The present invention is a block diagram showing a device for determining a real-time leakage rate of a main system of a nuclear power plant according to an exemplary embodiment. DETAILED DESCRIPTION

[0042] The present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.

[0043] The method disclosed herein can be executed by a terminal device, wherein the terminal device can be a server, a desktop computer, a laptop computer, a tablet computer, etc. The terminal device can also be, for example, a user device, a vehicle-mounted device, or a wearable device, etc. The embodiment of the present disclosure does not limit the type of terminal device. The method for determining the real-time leakage rate of the main system of a nuclear power plant disclosed herein includes:

[0044] Step 10, obtaining the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the beginning of the detection period, and obtaining the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the end of the detection period;

[0045] Step 11: Determine the leakage rate of the nuclear power plant main system during the detection period based on the liquid level changes of the control box, the liquid level changes of the pressurizer, and the temperature changes of the primary circuit during the detection period.

[0046] For example, step 11 includes: step 110, determining the leakage rate Fp of the nuclear power plant main system during the detection period according to formula 1:

[0047]

[0048] Among them, N1 is the liquid level of the control tank at the first time point, N3 is the liquid level of the pressurizer at the first time point, T1 is the average temperature of the primary circuit at the first time point, N2 is the liquid level of the control tank at the second time point, N4 is the liquid level of the pressurizer at the second time point, T2 is the average temperature of the primary circuit at the second time point, and Δt is the time from the first time point to the second time point.

[0049] The disclosed method for determining the real-time leakage rate of a nuclear power plant's main system determines the leakage rate of the plant's main system during a testing period based on changes in the liquid level of the control tank, the liquid level of the pressurizer, and the temperature of the primary circuit. This method collects main system parameters in real time and calculates the leakage rate, enabling timely and accurate monitoring of main system leakage, preventing human error and reducing human radiation exposure.

[0050] In a possible implementation, the method further includes:

[0051] Step 12: If it is detected that the control box drains water from the TEP header tank and / or replenishes water and boron from the control box during the detection period, the cumulative duration Δt' of the control box draining water from the TEP header tank and / or replenishing water and boron from the control box during the detection period, the liquid level change ΔN1 caused by the control box draining water from the TEP header tank, and the liquid level change ΔN2 caused by the control box replenishing water and boron;

[0052] The step 11 further includes: step 111, determining the leakage rate Fp of the nuclear power plant main system during the detection period according to formula 2:

[0053]

[0054] Where Δt' is the cumulative duration of the control box draining water to the TEP header box and / or replenishing water and boron from the control box during the detection period, ΔN1 is the absolute value of the liquid level change caused by the control box draining water to the TEP header box during the detection period, and ΔN2 is the absolute value of the liquid level change caused by the control box replenishing water and boron during the detection period. It should be noted that the same symbols in Formula 2 and Formula 1 have the same meanings and are not repeated here.

[0055] Because the liquid level in the control tank is controlled, it typically automatically drains to the TEP header tank when the level exceeds 1.47 meters. During periodic testing, inspectors also manually drain the tank based on test requirements. Furthermore, the tank's liquid level is also affected by water and boron replenishment. Step 111 of the present disclosure filters out parameters that could affect the normal leakage rate calculation based on the actual draining, water, and boron replenishment operations of the control tank, thereby more accurately calculating changes in the leakage rate.

[0056] In a possible implementation, the method further includes: step 13, setting multiple detection periods for the nuclear power plant main system, and for each of the multiple detection periods, using the methods of steps 10 and 11 to obtain the leakage rate of the nuclear power plant main system in the detection period.

[0057] In this way, the present invention can monitor the leakage rate of the main system throughout the entire process without the need for manual testing by personnel. The leakage rate of the main system can be calculated in real time without the participation of personnel and plotted as follows: Figure 1 The continuous curve is shown.

[0058] In one possible implementation, a device for determining a real-time leakage rate of a main system of a nuclear power plant includes:

[0059] a first acquisition module, configured to acquire the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the beginning of a detection period, and to acquire the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the end of the detection period;

[0060] The determination module is used to determine the leakage rate of the nuclear power plant main system during the detection period based on the liquid level changes of the control box during the detection period, the liquid level changes of the regulator during the detection period, and the temperature changes of the primary circuit during the detection period.

[0061] In a possible implementation, the determining module includes:

[0062] The first determination submodule is used to determine the leakage rate Fp of the nuclear power plant main system during the detection period according to Formula 1:

[0063]

[0064] Among them, N1 is the liquid level of the control tank at the first time point, N3 is the liquid level of the pressurizer at the first time point, T1 is the average temperature of the primary circuit at the first time point, N2 is the liquid level of the control tank at the second time point, N4 is the liquid level of the pressurizer at the second time point, T2 is the average temperature of the primary circuit at the second time point, and Δt is the time from the first time point to the second time point.

[0065] In a possible implementation, the apparatus further includes:

[0066] The second acquisition module is used to obtain, when it is detected that the control box drains water from the TEP header box and / or replenishes water and boron in the control box within the detection period, the cumulative duration Δt' of the control box draining water from the TEP header box and / or replenishing water and boron in the control box during the detection period, the liquid level change ΔN1 caused by the control box draining water from the TEP header box, and the liquid level change ΔN2 caused by the control box replenishing water and boron;

[0067] The determination module further includes: a second determination submodule, configured to determine the leakage rate Fp of the nuclear power plant main system during the detection period according to Formula 2:

[0068]

[0069] Among them, Δt' is the cumulative duration of the content control box draining water to the TEP header box and / or replenishing water and boron in the control box during the detection period, ΔN1 is the absolute value of the liquid level change caused by the content control box draining water to the TEP header box during the detection period, and ΔN2 is the absolute value of the liquid level change caused by the content control box replenishing water and boron in the detection period.

[0070] In a possible implementation, the apparatus further includes:

[0071] The overall detection module is used to set multiple detection periods for the main system of the nuclear power plant, and for each detection period in the multiple periods, use the first acquisition module and the determination module to determine the leakage rate of the main system of the nuclear power plant in the detection period.

[0072] The description of the above-mentioned device has been elaborated in detail in the description of the above-mentioned method, and will not be repeated here.

[0073] Figure 2 This is a block diagram illustrating an apparatus for determining the real-time leakage rate of a nuclear power plant primary system, according to an exemplary embodiment. For example, apparatus 800 may be a mobile phone, a computer, a digital broadcast terminal, a messaging device, a game console, a tablet device, a medical device, a fitness device, a personal digital assistant, or the like.

[0074] Reference Figure 2 , the device 800 may include one or more of the following components: a processing component 802 , a memory 804 , a power component 806 , a multimedia component 808 , an audio component 810 , an input / output (I / O) interface 812 , a sensor component 814 , and a communication component 816 .

[0075] The processing component 802 generally controls the overall operation of the device 800, such as operations associated with display, phone calls, data communications, camera operation, and recording operations. The processing component 802 may include one or more processors 820 to execute instructions to perform all or part of the steps of the device described above. In addition, the processing component 802 may include one or more modules to facilitate interaction between the processing component 802 and other components. For example, the processing component 802 may include a multimedia module to facilitate interaction between the multimedia component 808 and the processing component 802.

[0076] The memory 804 is configured to store various types of data to support operations on the device 800. Examples of such data include instructions for any application or device operating on the device 800, contact data, phone book data, messages, pictures, videos, etc. The memory 804 can be implemented by any type of volatile or non-volatile storage device, or a combination thereof, such as static random access memory (SRAM), electrically erasable programmable read-only memory (EEPROM), erasable programmable read-only memory (EPROM), programmable read-only memory (PROM), read-only memory (ROM), magnetic memory, flash memory, magnetic disk, or optical disk.

[0077] The power supply component 806 provides power to the various components of the device 800. The power supply component 806 may include a power management system, one or more power supplies, and other components associated with generating, managing, and distributing power to the device 800.

[0078] The multimedia component 808 includes a screen that provides an output interface between the device 800 and the user. In some embodiments, the screen may include a liquid crystal display (LCD) and a touch panel (TP). If the screen includes a touch panel, the screen may be implemented as a touch screen to receive input signals from the user. The touch panel includes one or more touch sensors to sense touches, slides, and gestures on the touch panel. The touch sensor can not only sense the boundaries of a touch or slide action, but also detect the duration and pressure associated with the touch or slide operation. In some embodiments, the multimedia component 808 includes a front camera and / or a rear camera. When the device 800 is in an operating mode, such as a shooting mode or a video mode, the front camera and / or the rear camera can receive external multimedia data. Each front camera and rear camera can be a fixed optical lens system or have focal length and optical zoom capabilities.

[0079] The audio component 810 is configured to output and / or input audio signals. For example, the audio component 810 includes a microphone (MIC), which is configured to receive external audio signals when the device 800 is in an operating mode, such as a call mode, a recording mode, and a voice recognition mode. The received audio signal can be further stored in the memory 804 or transmitted via the communication component 816. In some embodiments, the audio component 810 also includes a speaker for outputting audio signals.

[0080] I / O interface 812 provides an interface between processing component 802 and peripheral interface modules, such as a keyboard, click wheel, buttons, etc. These buttons may include but are not limited to: a home button, volume buttons, a start button, and a lock button.

[0081] The sensor assembly 814 includes one or more sensors for providing various aspects of the status assessment of the device 800. For example, the sensor assembly 814 can detect the open / closed state of the device 800, the relative positioning of components, such as the display and keypad of the device 800. The sensor assembly 814 can also detect changes in the position of the device 800 or a component of the device 800, the presence or absence of user contact with the device 800, the orientation or acceleration / deceleration of the device 800, and temperature changes of the device 800. The sensor assembly 814 may include a proximity sensor configured to detect the presence of nearby objects without any physical contact. The sensor assembly 814 may also include an optical sensor, such as a CMOS or CCD image sensor, for use in imaging applications. In some embodiments, the sensor assembly 814 may also include an accelerometer, a gyroscope sensor, a magnetic sensor, a pressure sensor, or a temperature sensor.

[0082] The communication component 816 is configured to facilitate wired or wireless communication between the device 800 and other devices. The device 800 can access a wireless network based on a communication standard, such as WiFi, 2G or 3G, or a combination thereof. In an exemplary embodiment, the communication component 816 receives a broadcast signal or broadcast-related information from an external broadcast management system via a broadcast channel. In an exemplary embodiment, the communication component 816 also includes a near field communication (NFC) module to facilitate short-range communication. For example, the NFC module can be implemented based on radio frequency identification (RFID) technology, infrared data association (IrDA) technology, ultra-wideband (UWB) technology, Bluetooth (BT) technology and other technologies.

[0083] In an exemplary embodiment, the apparatus 800 may be implemented by one or more application-specific integrated circuits (ASICs), digital signal processors (DSPs), digital signal processing devices (DSPDs), programmable logic devices (PLDs), field programmable gate arrays (FPGAs), controllers, microcontrollers, microprocessors, or other electronic components to perform the above-described method.

[0084] In an exemplary embodiment, a non-volatile computer-readable storage medium is also provided, such as a memory 804 including computer program instructions that can be executed by the processor 820 of the apparatus 800 to perform the above method.

[0085] Figure 3 1 is a block diagram of a device for determining a real-time leakage rate of a main system of a nuclear power plant according to an exemplary embodiment. For example, the device 1900 can be provided as a server. Figure 3 The apparatus 1900 includes a processing component 1922, which further includes one or more processors, and a memory resource represented by a memory 1932 for storing instructions, such as an application, that can be executed by the processing component 1922. The application stored in the memory 1932 may include one or more modules, each corresponding to a set of instructions. In addition, the processing component 1922 is configured to execute the instructions to perform the above-described method.

[0086] The device 1900 may also include a power supply component 1926 configured to perform power management of the device 1900, a wired or wireless network interface 1950 configured to connect the device 1900 to a network, and an input / output (I / O) interface 1958. The device 1900 may operate based on an operating system stored in the memory 1932, such as Windows Server™, MacOS X™, Unix™, Linux™, FreeBSD™, or the like.

[0087] In an exemplary embodiment, a non-volatile computer-readable storage medium is also provided, such as a memory 1932 including computer program instructions that can be executed by the processing component 1922 of the apparatus 1900 to perform the above-described method.

[0088] The present disclosure may be a system, method and / or computer program product. The computer program product may include a computer-readable storage medium carrying computer-readable program instructions for causing a processor to implement various aspects of the present disclosure.

[0089] A computer-readable storage medium can be a tangible device that can hold and store instructions for use by an instruction execution device. A computer-readable storage medium can be, for example, but not limited to, an electrical storage device, a magnetic storage device, an optical storage device, an electromagnetic storage device, a semiconductor storage device, or any suitable combination thereof. More specific examples (a non-exhaustive list) of computer-readable storage media include: a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), a static random access memory (SRAM), a portable compact disc read-only memory (CD-ROM), a digital versatile disk (DVD), a memory stick, a floppy disk, a mechanical encoding device, such as a punch card or a raised structure in a groove on which instructions are stored, and any suitable combination thereof. As used herein, a computer-readable storage medium is not to be construed as a transient signal per se, such as a radio wave or other freely propagating electromagnetic wave, an electromagnetic wave propagating through a waveguide or other transmission medium (e.g., a light pulse through a fiber optic cable), or an electrical signal transmitted through an electrical wire.

[0090] The computer-readable program instructions described herein can be downloaded from a computer-readable storage medium to each computing / processing device, or downloaded to an external computer or external storage device via a network, such as the Internet, a local area network, a wide area network, and / or a wireless network. The network can include copper transmission cables, fiber optic transmission, wireless transmission, routers, firewalls, switches, gateway computers, and / or edge servers. The network adapter card or network interface in each computing / processing device receives the computer-readable program instructions from the network and forwards the computer-readable program instructions to be stored in the computer-readable storage medium in each computing / processing device.

[0091] The computer program instructions for performing the operations of the present disclosure may be assembly instructions, instruction set architecture (ISA) instructions, machine instructions, machine-dependent instructions, microcode, firmware instructions, state setting data, or source code or object code written in any combination of one or more programming languages, including object-oriented programming languages ​​such as Smalltalk, C++, and conventional procedural programming languages ​​such as "C" language or similar programming languages. Computer-readable program instructions may be executed entirely on a user's computer, partially on a user's computer, as an independent software package, partially on a user's computer, partially on a remote computer, or entirely on a remote computer or server. In the case of a remote computer, the remote computer may be connected to the user's computer via any type of network, including a local area network (LAN) or a wide area network (WAN), or may be connected to an external computer (e.g., utilizing an Internet service provider to connect via the Internet). In some embodiments, an electronic circuit, such as a programmable logic circuit, a field programmable gate array (FPGA), or a programmable logic array (PLA), may be personalized by utilizing the state information of the computer-readable program instructions. The electronic circuit may execute the computer-readable program instructions, thereby realizing various aspects of the present disclosure.

[0092] Various aspects of the present disclosure are described herein with reference to flowcharts and / or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of the present disclosure. It should be understood that each block of the flowcharts and / or block diagrams, and combinations of blocks in the flowcharts and / or block diagrams, can be implemented by computer-readable program instructions.

[0093] These computer-readable program instructions can be provided to a processor of a general-purpose computer, a special-purpose computer, or other programmable data processing device, thereby producing a machine, so that when these instructions are executed by the processor of the computer or other programmable data processing device, a device is generated that implements the functions / actions specified in one or more blocks in the flowchart and / or block diagram. These computer-readable program instructions can also be stored in a computer-readable storage medium, where these instructions cause the computer, programmable data processing device, and / or other device to operate in a specific manner. Thus, the computer-readable medium storing the instructions comprises an article of manufacture that includes instructions for implementing various aspects of the functions / actions specified in one or more blocks in the flowchart and / or block diagram.

[0094] Computer-readable program instructions may also be loaded onto a computer, other programmable data processing apparatus, or other device so that a series of operational steps are performed on the computer, other programmable data processing apparatus, or other device to produce a computer-implemented process, thereby causing the instructions executed on the computer, other programmable data processing apparatus, or other device to implement the functions / actions specified in one or more blocks in the flowchart and / or block diagram.

[0095] The flow charts and block diagrams in the accompanying drawings show the possible architecture, functions and operations of the systems, methods and computer program products according to multiple embodiments of the present disclosure. In this regard, each box in the flow chart or block diagram can represent a part of a module, program segment or instruction, and the part of the module, program segment or instruction contains one or more executable instructions for realizing the prescribed logical function. In some alternative implementations, the functions marked in the box can also occur in a sequence different from that marked in the accompanying drawings. For example, two consecutive boxes can actually be executed substantially in parallel, and they can sometimes be executed in the opposite order, depending on the functions involved. It should also be noted that each box in the block diagram and / or flow chart, and the combination of the boxes in the block diagram and / or flow chart can be implemented by a dedicated hardware-based system that performs the prescribed function or action, or can be implemented by a combination of dedicated hardware and computer instructions.

[0096] While various embodiments of the present disclosure have been described above, the foregoing description is intended to be illustrative, non-exhaustive, and not limited to the disclosed embodiments. Many modifications and variations will be apparent to those skilled in the art without departing from the scope and spirit of the described embodiments. The terminology used herein is selected to best explain the principles of the embodiments, their practical applications, or technical improvements to existing technologies, or to enable others skilled in the art to understand the embodiments disclosed herein.

Claims

1. A method for determining the real-time leakage rate of a nuclear power plant main system, characterized in that: The method comprises: Step 10, obtaining the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the beginning of the detection period, and obtaining the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the end of the detection period; Step 11, determining the leakage rate of the nuclear power plant main system during the detection period based on the liquid level change of the control box during the detection period, the liquid level change of the pressurizer during the detection period, and the temperature change of the primary circuit during the detection period; Step 11 includes: Step 110: Determine the leakage rate Fp of the nuclear power plant main system during the detection period according to Formula 1: Formula 1 Wherein, N1 is the liquid level of the control tank at the first time point, N3 is the liquid level of the pressurizer at the first time point, T1 is the average temperature of the primary circuit at the first time point, N2 is the liquid level of the control tank at the second time point, N4 is the liquid level of the pressurizer at the second time point, T2 is the average temperature of the primary circuit at the second time point, and Δt is the time from the first time point to the second time point; The method further comprises: Step 12: If it is detected that the control box drains water from the TEP header tank and / or replenishes water and boron from the control box during the detection period, the cumulative duration Δt' of the control box draining water from the TEP header tank and / or replenishing water and boron from the control box during the detection period, the liquid level change ΔN1 caused by the control box draining water from the TEP header tank, and the liquid level change ΔN2 caused by the control box replenishing water and boron; The step 11 further includes: step 111, determining the leakage rate Fp of the nuclear power plant main system during the detection period according to formula 2: Formula 2 Among them, Δt' is the cumulative duration of the content control box draining water to the TEP header box and / or replenishing water and boron in the control box during the detection period, ΔN1 is the absolute value of the liquid level change caused by the content control box draining water to the TEP header box during the detection period, and ΔN2 is the absolute value of the liquid level change caused by the content control box replenishing water and boron in the detection period.

2. The method according to claim 1, characterized in that The method further comprises: Step 13: Set multiple detection periods for the main system of the nuclear power plant, and for each of the multiple detection periods, use the methods of steps 10 and 11 to obtain the leakage rate of the main system of the nuclear power plant during the detection period.

3. A device for determining the real-time leakage rate of a nuclear power plant main system, characterized in that: The device comprises: a first acquisition module, configured to acquire the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the beginning of a detection period, and to acquire the liquid level of the control tank, the liquid level of the pressurizer, and the average temperature of the primary circuit at the end of the detection period; a determination module, for determining the leakage rate of the nuclear power plant main system during the detection period based on the liquid level change of the control box during the detection period, the liquid level change of the pressurizer during the detection period, and the temperature change of the primary circuit during the detection period; The modules to be determined include: The first determination submodule is used to determine the leakage rate Fp of the nuclear power plant main system during the detection period according to Formula 1: Formula 1 Wherein, N1 is the liquid level of the control tank at the first time point, N3 is the liquid level of the pressurizer at the first time point, T1 is the average temperature of the primary circuit at the first time point, N2 is the liquid level of the control tank at the second time point, N4 is the liquid level of the pressurizer at the second time point, T2 is the average temperature of the primary circuit at the second time point, and Δt is the time from the first time point to the second time point; The device further comprises: The second acquisition module is used to obtain, when it is detected that the control box drains water from the TEP header box and / or replenishes water and boron in the control box within the detection period, the cumulative duration Δt' of the control box draining water from the TEP header box and / or replenishing water and boron in the control box during the detection period, the liquid level change ΔN1 caused by the control box draining water from the TEP header box, and the liquid level change ΔN2 caused by the control box replenishing water and boron; The determination module further includes: a second determination submodule, configured to determine the leakage rate Fp of the nuclear power plant main system during the detection period according to Formula 2: Formula 2 Among them, Δt' is the cumulative duration of the content control box draining water to the TEP header box and / or replenishing water and boron in the control box during the detection period, ΔN1 is the absolute value of the liquid level change caused by the content control box draining water to the TEP header box during the detection period, and ΔN2 is the absolute value of the liquid level change caused by the content control box replenishing water and boron in the detection period.

4. The device according to claim 3, characterized in that The device further comprises: The overall detection module is used to set multiple detection periods for the main system of the nuclear power plant, and for each detection period in the multiple periods, use the first acquisition module and the determination module to determine the leakage rate of the main system of the nuclear power plant in the detection period.

5. A device for determining the real-time leakage rate of a nuclear power plant main system, characterized in that: The device comprises: processor; a memory for storing processor-executable instructions; The processor is configured to execute the method of claim 1 or 2.

6. A non-volatile computer-readable storage medium having computer program instructions stored thereon, characterized in that: When the computer program instructions are executed by a processor, the method according to claim 1 or 2 is implemented.

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