Monitoring Method and Device for Uncertainty of Primary Loop Leakage Rate in Pressurized Water Reactor Nuclear Power Plant

Abstract

This application relates to a method and device for monitoring the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant. The method includes: obtaining the uncertainty influence parameters of the primary loop of the pressurized water reactor nuclear power plant at two adjacent times; determining the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later time among the two adjacent times according to the uncertainty influence parameters at the two adjacent times; wherein, the uncertainty influence parameters include at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of the pressurized water reactor nuclear power plant; wherein, the uncertainty influence parameters at each time are obtained by the following method: determining the uncertainty influence parameters at the corresponding time according to the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding time. Using this method can improve the accuracy of the uncertainty of the primary loop leakage rate of the pressurized water reactor nuclear power plant.

Description

Technical Field

[0001] The present application relates to the field of nuclear power technology, and particularly to a method and device for monitoring the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant. Background Art

[0002] In the field of nuclear power, the primary loop of a pressurized water reactor nuclear power plant mainly undertakes the responsibility of ensuring the normal operation of the reactor and its systems, and works in coordination with the secondary loop to be responsible for heating the core of the pressurized water reactor. Therefore, the primary loop of a pressurized water reactor nuclear power plant plays a crucial role in the combustion process of the nuclear reactor. In order to ensure the safe operation of the primary loop of a pressurized water reactor nuclear power plant, it is necessary to regularly conduct a coolant leakage rate test on the primary loop of the pressurized water reactor nuclear power plant to monitor the leakage rate of the coolant in the primary loop.

[0003] However, in the related art, the coolant leakage rate test usually first determines the initial leakage rate based on the collected data, and then adjusts the initial leakage rate according to the preset leakage rate uncertainty to obtain a more accurate target leakage rate. However, in actual operation, the leakage rate uncertainty at different times is not constant. Therefore, in order to improve the accuracy of the target leakage rate, it is necessary to monitor the uncertainty of the leakage rate in real time. Summary of the Invention

[0004] Based on this, in view of the above technical problems, it is necessary to provide a method, device and product for monitoring the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant that can improve the accuracy of the leakage rate uncertainty.

[0005] In a first aspect, the present application provides a method for monitoring the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant, including:

[0006] Obtain the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent times;

[0007] Determine the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant at the later time among the two adjacent times according to the uncertainty influence parameters at the two adjacent times; wherein, the uncertainty influence parameters include at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of a pressurized water reactor nuclear power plant;

[0008] Wherein, the uncertainty influence parameter at each time is obtained by the following method:

[0009] Determine the uncertainty influence parameter at the corresponding time according to the liquid state data corresponding to the target container in the primary loop of a pressurized water reactor nuclear power plant at the corresponding time.

[0010] In one embodiment, the uncertainty influence parameter at a corresponding moment is determined according to the liquid state data of the target container in the primary loop of a pressurized water reactor nuclear power plant, including: for each of two adjacent moments, the density data of the liquid in the target container at this moment is determined according to the liquid state data of the target container at this moment; the liquid state data includes the liquid mass and liquid volume of the liquid in the target container; the uncertainty influence parameter of the primary loop of the pressurized water reactor nuclear power plant at this moment is determined according to the density data.

[0011] In one embodiment, determining the density data of the liquid in the target container at a moment according to the liquid state data of the target container at this moment includes: obtaining the primary loop environment data and the preset primary loop environment uncertainty at this moment; determining the density data of the liquid in the target container at this moment according to the liquid state data of the target container at this moment, the primary loop environment data, and the primary loop environment uncertainty.

[0012] In one embodiment, the primary loop environment data includes the pressure data and temperature data of the primary loop of a pressurized water reactor nuclear power plant. Correspondingly, the primary loop environment uncertainty includes temperature uncertainty and pressure uncertainty; determining the density data of the liquid in the target container at a moment according to the liquid state data of the target container at this moment, the primary loop environment data, and the primary loop environment uncertainty includes: correcting the pressure data at this moment according to the pressure uncertainty to obtain the corrected pressure data at this moment; and correcting the temperature data at this moment according to the temperature uncertainty to obtain the corrected temperature data at this moment; determining the different density data corresponding to different primary loop environment data of the liquid in the target container at this moment according to the pressure data, the corrected pressure data, the temperature data, the corrected temperature data, and the liquid state data.

[0013] In one embodiment, determining the uncertainty influence parameter of the target container at a moment according to the density data includes: obtaining the primary loop environment uncertainty at this moment; wherein, the primary loop environment uncertainty includes the uncertainty of the volume control tank liquid level, the uncertainty of the relief tank liquid level, the uncertainty of the accumulator tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the sump buffer tank liquid level, and the uncertainty of the leakage measurement container liquid level; determining the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant according to each density data, the temperature uncertainty, and the pressure uncertainty; determining the container volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at this moment according to the fluid volume uncertainty and the volume control tank liquid level uncertainty; determining the container volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at a moment according to the uncertainty of the accumulator tank liquid level, the uncertainty of the relief tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the sump buffer tank liquid level, and the uncertainty of the leakage measurement container liquid level.

[0014] In one embodiment, according to each density data, temperature uncertainty, and pressure uncertainty, the fluid volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant is determined, including: determining a first rate of change and a second rate of change of the primary loop of the pressurized water reactor nuclear power plant at a moment according to each density data, pressure uncertainty, and temperature uncertainty; wherein, the first rate of change represents the rate of change of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to temperature change; the second rate of change represents the rate of change of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to pressure change; determining the fluid mass uncertainty of the primary loop of the pressurized water reactor nuclear power plant at a moment according to the first rate of change, the second rate of change, temperature uncertainty, and pressure uncertainty; and determining the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at a moment according to the fluid mass uncertainty and each density data.

[0015] In one embodiment, the leakage rate uncertainty includes a first leakage rate uncertainty, a second leakage rate uncertainty, and a third leakage rate uncertainty; wherein, the first leakage rate uncertainty represents the overall leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant; the second leakage rate uncertainty represents the measurement uncertainty of the primary loop of the pressurized water reactor nuclear power plant; the third leakage rate uncertainty represents the prediction uncertainty of the primary loop of the pressurized water reactor nuclear power plant; determining the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later moment among two adjacent moments according to the uncertainty influence parameters at two adjacent moments, including: determining the first leakage rate uncertainty according to the container volume uncertainty at two adjacent moments and the time difference between two adjacent moments; determining the second leakage rate uncertainty according to the container volume uncertainty at two adjacent moments; and determining the third leakage rate uncertainty according to the first leakage rate uncertainty and the container volume uncertainty at the earlier moment among two adjacent moments.

[0016] In a second aspect, the present application also provides a monitoring device for the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant, including:

[0017] a data acquisition module, which acquires the uncertainty influence parameters of the primary loop of the pressurized water reactor nuclear power plant at two adjacent moments;

[0018] an uncertainty determination module, which determines the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later moment among two adjacent moments according to the uncertainty influence parameters at two adjacent moments; wherein, the uncertainty influence parameters include at least one of the container volume uncertainty and the container volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant;

[0019] wherein, the uncertainty influence parameters at each moment are obtained by the following method:

[0020] An influence parameter determination module determines the uncertainty influence parameter at a corresponding moment according to the liquid state data corresponding to a target container in the primary loop of a pressurized water reactor nuclear power plant at the corresponding moment.

[0021] Thirdly, the present application also provides a computer device, including a memory and a processor. The memory stores a computer program, and when the processor executes the computer program, the following steps are implemented:

[0022] Obtain the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent moments;

[0023] Determine the leakage rate uncertainty at the later moment among two adjacent moments of the primary loop of a pressurized water reactor nuclear power plant according to the uncertainty influence parameters at two adjacent moments; wherein, the uncertainty influence parameter includes at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of a pressurized water reactor nuclear power plant;

[0024] Wherein, the uncertainty influence parameter at each moment is obtained by the following method:

[0025] Determine the uncertainty influence parameter at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of a pressurized water reactor nuclear power plant at the corresponding moment.

[0026] Fourthly, the present application also provides a computer-readable storage medium, on which a computer program is stored. When the computer program is executed by a processor, the following steps are implemented:

[0027] Obtain the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent moments;

[0028] Determine the leakage rate uncertainty at the later moment among two adjacent moments of the primary loop of a pressurized water reactor nuclear power plant according to the uncertainty influence parameters at two adjacent moments; wherein, the uncertainty influence parameter includes at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of a pressurized water reactor nuclear power plant;

[0029] Wherein, the uncertainty influence parameter at each moment is obtained by the following method:

[0030] Determine the uncertainty influence parameter at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of a pressurized water reactor nuclear power plant at the corresponding moment.

[0031] Fifthly, the present application also provides a computer program product, including a computer program. When the computer program is executed by a processor, the following steps are implemented:

[0032] Obtain the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent moments;

[0033] Determine the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant at the later moment among two adjacent moments according to the uncertainty influence parameters at two adjacent moments; wherein, the uncertainty influence parameters include at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of the pressurized water reactor nuclear power plant.

[0034] Among them, the uncertainty influence parameters at each moment are obtained in the following manner:

[0035] Determine the uncertainty influence parameters at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding moment.

[0036] The above-mentioned method and device for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant determine the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later moment among two adjacent moments according to the uncertainty influence parameters at two adjacent moments. Since the uncertainty influence parameters at different moments are determined based on the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding moment, therefore, the uncertainty influence parameters corresponding to different moments are affected by the state of the liquid in the target container at the corresponding moment. That is, the uncertainty influence parameters can more accurately characterize the state of the primary loop of the pressurized water reactor nuclear power plant at the corresponding moment. Further, the leakage rate uncertainty determined based on the uncertainty influence parameters at two adjacent moments is also accurate. That is to say, the above method can not only monitor the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant in real time, but also ensure the accuracy of the leakage rate uncertainty. Description of the Drawings

[0037] In order to more clearly illustrate the technical solutions in the embodiments of the present application or related technologies, the following will briefly introduce the drawings required for use in the description of the embodiments or related technologies. Obviously, the drawings in the following description are only some embodiments of the present application. For those of ordinary skill in the art, without creative efforts, other drawings can also be obtained based on these drawings.

[0038] Figure 1 It is an application diagram of a method for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant provided in this embodiment;

[0039] Figure 2 It is a schematic flow chart of a method for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant provided in this embodiment;

[0040] Figure 3 It is a schematic flow chart of a method for determining the uncertainty influence parameters provided in this embodiment;

[0041] Figure 4Schematic flowchart of a method for determining leakage rate uncertainty provided in this embodiment;

[0042] Figure 5 Schematic flowchart of another method for monitoring the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant provided in this embodiment;

[0043] Figure 6 Structural block diagram of a device for monitoring the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant provided in this embodiment;

[0044] Figure 7 Internal structure diagram of a computer device provided in this embodiment. Detailed implementation manners

[0045] In order to make the objectives, technical solutions and advantages of the present application clearer, the present application will be further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and are not used to limit the present application.

[0046] Before introducing the embodiments of the present application, it should be noted that in the field of nuclear power technology, a huge amount of heat energy is generated by nuclear fuel fission in the reactor core. The water pumped into the core by the main pump is heated to a certain temperature, for example, 327 degrees, and a certain atmospheric pressure, for example, 155 atmospheres of high-temperature and high-pressure water. The high-temperature and high-pressure water flows through the heat transfer U-shaped tubes in the steam generator, and transfers the heat energy to the secondary loop cooling water outside the U-shaped tubes through the tube wall. After releasing the heat, it is pumped back into the core by the main pump to be reheated and then enters the steam generator. The water circulates continuously in the closed loop in this way, which is called the primary loop. The primary loop of a pressurized water reactor nuclear power plant plays a crucial role in the combustion process of the nuclear reactor.

[0047] However, the primary loop is radioactive. When a small-break loss-of-coolant accident occurs in a pressurized water reactor, the radioactive substances in the reactor coolant may enter the containment and may leak through the containment, causing pollution to the primary loop environment. Secondly, when the accident occurs, the coolant at the break suddenly loses pressure, which may form a strong shock wave in the primary loop system. This shock wave may damage the core structure and cause the pipes to swing, further damaging the facilities inside the containment. That is to say, a serious leakage of the primary loop of a pressurized water reactor nuclear power plant will lead to a major accident. Therefore, usually, the staff will regularly calculate the leakage rate of the primary loop of a pressurized water reactor nuclear power plant to ensure that the leakage rate of the primary loop of a pressurized water reactor nuclear power plant is controlled within a safe range.

[0048] In the process of determining the leakage rate of the primary loop of a pressurized water reactor nuclear power plant, the leakage rate uncertainty is usually introduced to calibrate the measured leakage rate of the primary loop of the pressurized water reactor nuclear power plant. However, in traditional technologies, the leakage rate uncertainty is usually pre-determined based on manual experience, which is inaccurate and can lead to inaccurate leakage rates of the primary loop of the pressurized water reactor nuclear power plant. To improve the accuracy of the leakage rate of the primary loop of the pressurized water reactor nuclear power plant, the embodiments of the present application provide a method capable of real-time monitoring of the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant, improving the accuracy of the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant, and thus achieving the purpose of improving the accuracy of the leakage rate of the primary loop of the pressurized water reactor nuclear power plant.

[0049] The method for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant provided by the embodiments of the present application can be applied to an application environment as shown in Figure 1 In the figure. Among them, the terminal 102 communicates with the server 104 through the network. The data storage system can store the data that the server 104 needs to process. The data storage system can be integrated on the server 104, or can be placed on the cloud or other network servers. Specifically, the server 104 obtains the uncertainty influence parameters of the primary loop of the pressurized water reactor nuclear power plant at two adjacent times, and determines the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later time among the two adjacent times according to the uncertainty influence parameters at the two adjacent times. And the leakage rate uncertainty is displayed through the terminal 102. Among them, the uncertainty influence parameters include at least one of the container volume uncertainty and the container capacity uncertainty. Among them, the determination method of the uncertainty influence parameters at each time is: the server 104 determines the uncertainty influence parameters at the corresponding time according to the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding time. Among them, the terminal 102 can be, but is not limited to, various personal computers, laptop computers, smart phones, tablet computers, Internet of Things devices and portable wearable devices. The Internet of Things devices can be smart speakers, smart TVs, smart air conditioners, smart in-vehicle devices, etc. The portable wearable devices can be smart watches, smart bracelets, head-mounted devices, etc. The server 104 can be implemented by an independent server or a server cluster composed of multiple servers.

[0050] In one embodiment, as shown in Figure 2 In the figure, a method for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant is provided. Taking the method applied to the server 104 in Figure 1 as an example, the following steps are included:

[0051] S201, obtain the uncertainty influence parameters of the primary loop of the pressurized water reactor nuclear power plant at two adjacent times.

[0052] Among them, the uncertainty influence parameter at each moment characterizes the parameter that can affect the uncertainty of the leakage rate of the primary loop of a pressurized water reactor nuclear power plant at that moment. Exemplarily, the uncertainty influence parameter includes at least one of the uncertainty of the container volume and the uncertainty of the container capacity of the primary loop of the pressurized water reactor nuclear power plant. The container in the primary loop of the pressurized water reactor nuclear power plant represents the reactor pressure vessel in the primary loop of the pressurized water reactor nuclear power plant. The embodiment of the present application does not limit the time difference between two adjacent moments.

[0053] Exemplarily, in two adjacent moments of this embodiment, the uncertainty influence parameter of the previous moment has been determined when determining the corresponding leakage rate of the primary loop of the pressurized water reactor nuclear power plant, and it can be stored in the corresponding database and directly obtained from the database when determining the leakage rate of the primary loop of the pressurized water reactor nuclear power plant at the subsequent moment. Among two adjacent moments, the uncertainty influence parameter of the subsequent moment can be determined by the present server in the following manner, or can be determined by a server associated with the present server in the following manner or other manners capable of determining the uncertainty influence parameter, and this is not limited.

[0054] In an alternative embodiment, among two adjacent moments, the uncertainty influence parameters at different moments can all be obtained in the following manner: Determine the uncertainty influence parameter at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding moment.

[0055] Among them, the liquid state data is used to characterize the state data of the liquid in the reactor pressure vessel in the primary loop of the pressurized water reactor nuclear power plant. For example, it can characterize at least one of the state data such as the temperature, volume, and density of the liquid.

[0056] In an alternative embodiment, the liquid state data can be input into a pre-trained uncertainty influence parameter determination model to obtain the uncertainty influence parameter at the corresponding moment. It should be noted that the embodiment of the present application does not make any limitation on the construction method and training process of the uncertainty influence parameter determination model.

[0057] S202. Determine the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the subsequent moment among two adjacent moments according to the uncertainty influence parameters at two adjacent moments.

[0058] In an alternative embodiment, the uncertainty influence parameters at two adjacent moments can be input into a pre-trained non-leakage rate uncertainty determination model to obtain the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the subsequent moment among two adjacent moments.

[0059] In another alternative embodiment, the uncertainty influence parameters at two adjacent times can be processed according to a pre-determined leakage rate uncertainty determination formula to obtain the leakage rate uncertainty at the later time among two adjacent times in the primary loop of a pressurized water reactor nuclear power plant.

[0060] It should be noted that the present application embodiment does not make any limitations on the construction method and training process of the leakage rate uncertainty determination model. The uncertainty determination formula can be determined based on artificial experience or through a large number of experiments, and no limitations are imposed on this.

[0061] In the above-mentioned method for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant, the leakage rate uncertainty at the later time among two adjacent times in the primary loop of a pressurized water reactor nuclear power plant is determined according to the uncertainty influence parameters at two adjacent times in the primary loop of a pressurized water reactor nuclear power plant. Since the uncertainty influence parameters at different times are determined based on the liquid state data corresponding to the target container in the primary loop of a pressurized water reactor nuclear power plant at the corresponding times, the uncertainty influence parameters corresponding to different times are affected by the state of the liquid in the target container at the corresponding times. That is, the uncertainty influence parameters can more accurately characterize the state of the primary loop of a pressurized water reactor nuclear power plant at the corresponding times. Further, the leakage rate uncertainty determined based on the uncertainty influence parameters at two adjacent times is also accurate. That is to say, the above method can not only monitor the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant in real time, but also ensure the accuracy of the leakage rate uncertainty.

[0062] On the basis of the above embodiments, further, in order to improve the accuracy of the uncertainty influence parameters at each time, in one embodiment, a specific method for determining the uncertainty influence parameters at different times is provided, as Figure 3 shown, including the following steps:

[0063] S301, for each of two adjacent times, determine the density data of the liquid in the target container according to the liquid state data of the target container at this time.

[0064] Among them, the target container can be any container in the primary loop of a pressurized water reactor nuclear power plant. For example, it can be a volume control tank. The liquid state data includes the liquid mass and liquid volume of the liquid in the container.

[0065] In an alternative embodiment, in this embodiment, the ratio of the liquid mass to the liquid volume of the liquid in the target container at this time can be directly used as the density data of the liquid in the target container at this time.

[0066] In another optional embodiment, to improve the accuracy of the density data of the liquid in the target container at different times, during the process of determining the density data, the influence of the primary loop environmental uncertainty on the density data is introduced. The primary loop environmental uncertainty includes temperature uncertainty and pressure uncertainty; correspondingly, determining the density data of the liquid in the target container at this moment includes the following steps: obtaining the environmental data at this moment and the preset primary loop environmental uncertainty; determining the density data of the liquid in the target container at this moment according to the liquid state data, the primary loop environmental data, and the primary loop environmental uncertainty of the target container at this moment. Among them, the primary loop environmental data may include at least one of environmental data such as temperature data and pressure data in the primary loop. The primary loop environmental uncertainty is used to characterize the uncertainty between the collected environmental data and the actual environmental data. The primary loop environmental uncertainty can be determined manually or obtained through a large number of experiments, and this is not limited.

[0067] Exemplarily, in this embodiment, the primary loop environmental data of the container at this moment can be obtained through a sensor, and the liquid state data, the primary loop environmental data, and the preset primary loop environmental uncertainty at this moment are input into a pre-determined density data determination model to obtain the density data of the liquid in the target container at this moment. It can also be to process the liquid state data, the primary loop environmental data, and the preset primary loop environmental uncertainty at this moment according to a pre-determined density data determination formula to obtain the density data of the liquid in the target container at this moment.

[0068] It should be noted that the embodiments of the present application do not limit the construction method and training process of the density data determination model. The density data determination formula can be determined based on manual experience or determined through a large number of experiments, and this is not limited.

[0069] To make the process of determining the density data in this embodiment more detailed, the embodiments of the present application take the primary loop environment including pressure data and temperature data, and the primary loop environmental uncertainty including temperature uncertainty and pressure uncertainty as an example to elaborate on determining the density data of the liquid in the target container at different times: correcting the pressure data at this moment according to the pressure uncertainty to obtain the corrected pressure data at this moment; and correcting the temperature data at this moment according to the temperature uncertainty to obtain the corrected temperature data at this moment; determining the different density data corresponding to different primary loop environmental data of the target container at different containers at this moment according to the pressure data, the corrected pressure data, the temperature data, the corrected temperature data, and the liquid state data. Among them, the corrected pressure data represents the corrected pressure data. The corrected temperature data represents the corrected temperature data.

[0070] For example, the pressure data can be corrected based on the following formula:

[0071] P' = P + B;

[0072] In the formula, P' represents the corrected pressure data; P represents the pressure data; B represents the pressure uncertainty.

[0073] The temperature data can be corrected based on the following formula:

[0074] T' = T + A;

[0075] In the formula, T' represents the corrected temperature data; T represents the temperature data; A represents the temperature uncertainty.

[0076] Further, in this embodiment, the "pressure data P, temperature data T, and liquid state data", "pressure data P, corrected temperature data T', and liquid state data", and "corrected pressure data P', temperature data T, and liquid state data" can be respectively used as input data and input into the density data determination model to obtain different density data corresponding to the three types of input data, such as ρ1, ρ2, and ρ3.

[0077] S302. Determine the uncertainty influence parameter of the primary loop of the pressurized water reactor nuclear power plant at this moment according to the density data.

[0078] In an alternative embodiment, the density data can be input into a pre-trained uncertainty influence parameter determination model to obtain the uncertainty influence parameter of the primary loop of the pressurized water reactor nuclear power plant at this moment.

[0079] In another alternative embodiment, it can also be determined in the following way: Obtain the uncertainty of the primary loop environment at this moment; wherein, the uncertainty of the primary loop environment includes the uncertainty of the volume control tank liquid level, the uncertainty of the accumulator tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the sump buffer tank liquid level, and the uncertainty of the leakage measurement container liquid level. According to each density data, temperature uncertainty, and pressure uncertainty, determine the uncertainty of the fluid volume of the primary loop of the pressurized water reactor nuclear power plant; According to the uncertainty of the fluid volume and the uncertainty of the volume control tank liquid level, determine the uncertainty of the container volume of the primary loop of the pressurized water reactor nuclear power plant at this moment; According to the uncertainty of the accumulator tank liquid level, the uncertainty of the pressure relief tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the sump buffer tank liquid level, and the uncertainty of the leakage measurement container liquid level, determine the uncertainty of the container volume of the primary loop of the pressurized water reactor nuclear power plant at this moment. Among them, the leakage measurement container can be the O-ring leakage measurement container of the reactor pressure vessel; the uncertainty of the volume control tank liquid level, the uncertainty of the accumulator tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the sump buffer tank liquid level, and the uncertainty of the leakage measurement container liquid level respectively represent the uncertainty of the collected data corresponding to different liquid tanks other than the target container.

[0080] In an alternative embodiment, each density data, temperature uncertainty, and pressure uncertainty can be input into a pre-determined liquid volume uncertainty determination model to obtain the liquid volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant. Subsequently, the fluid volume uncertainty and the volume control tank liquid level uncertainty are input into a pre-determined container volume uncertainty determination model to obtain the container volume uncertainty. Similarly, the accumulator tank liquid level uncertainty, the drain tank liquid level uncertainty, the sump buffer tank liquid level uncertainty, and the letdown measurement container liquid level uncertainty are input into a pre-determined container volume uncertainty determination model to determine the container volume uncertainty. Among them, each model can be a neural network model or a calculation formula. When the model is a neural network model, the embodiments of the present application do not limit the construction method and training process of each model. When the model is a calculation formula, the calculation formula can be determined based on artificial experience or through a large number of experiments, and this is not limited.

[0081] Further, in another alternative embodiment, the fluid volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant can be determined in the following manner: according to each density data, pressure uncertainty, and temperature uncertainty, determine the first change rate and the second change rate of the primary loop of the pressurized water reactor nuclear power plant at a certain moment; wherein, the first change rate represents the change rate of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to the change in temperature; the second change rate represents the change rate of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to the change in pressure; according to the first change rate, the second change rate, temperature uncertainty, and pressure uncertainty, determine the fluid mass uncertainty of the primary loop of the pressurized water reactor nuclear power plant at this moment; according to the fluid mass uncertainty and each density data, determine the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at a certain moment.

[0082] Exemplarily, the first change rate can be determined by the following formula:

[0083] ;

[0084] In the formula, represents the first change rate; ρ2 represents the density data determined with "pressure data P, corrected temperature data T', and liquid state data" as input data; ρ1 represents the density data determined with "pressure data P, temperature data T, and liquid state data" as input data; A represents the temperature uncertainty.

[0085] Exemplarily, the second change rate can be determined by the following formula:

[0086] ;

[0087] In the formula, represents the second rate of change; ρ3 represents the density data determined with "corrected pressure data P', temperature data T, and liquid state data" as input data; ρ1 represents the density data determined with "pressure data P, temperature data T, and liquid state data" as input data; B represents the pressure uncertainty.

[0088] Exemplarily, the fluid mass uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment can be determined by the following formula:

[0089] ;

[0090] In the formula, represents the fluid mass uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment; represents the first rate of change; represents the second rate of change; A represents the temperature uncertainty; B represents the pressure uncertainty.

[0091] Exemplarily, the fluid volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant at a moment can be determined by the following formula:

[0092] ;

[0093] In the formula, represents the fluid volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment; represents the fluid mass uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment.

[0094] Furthermore, the container volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment can be determined by the following formula:

[0095] ;

[0096] In the formula, represents the container volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment; represents the fluid volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment; C represents the volume control tank liquid level uncertainty.

[0097] Exemplarily, the container volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment can be determined by the following formula:

[0098] ;

[0099] In the formula, W represents the container volume uncertainty of the primary loop of a pressurized water reactor nuclear power plant at this moment; D represents the relief tank liquid level uncertainty; E represents the accumulator tank liquid level uncertainty; F represents the drain tank liquid level uncertainty; G represents the sump buffer tank liquid level uncertainty; H represents the letdown measurement container liquid level uncertainty.

[0100] In the above embodiments, in the process of determining the density data of the liquid in the container at different times, the influence of the primary loop environment data and the uncertainty of the primary loop environment on the density data is considered, so that the determined density data is more accurate, and further, the uncertainty influence parameter of the primary loop of the pressurized water reactor nuclear power plant determined according to the density data is more accurate.

[0101] On the basis of the above embodiments, further, in one embodiment, the leakage rate uncertainty includes a first leakage rate uncertainty, a second leakage rate uncertainty, and a third leakage rate uncertainty. Correspondingly, as Figure 4 shown, the method for determining the leakage rate uncertainty at the later time in two adjacent times of the primary loop of the pressurized water reactor nuclear power plant may include the following steps:

[0102] S401, determine the first leakage rate uncertainty according to the container volume uncertainty at two adjacent times and the time difference between the two adjacent times.

[0103] Among them, the first leakage rate uncertainty characterizes the overall uncertainty of the primary loop of the pressurized water reactor nuclear power plant, that is, the total uncertainty of the leakage rate.

[0104] In an alternative embodiment, the container volume uncertainty at two adjacent times and the time difference between the two adjacent times may be input into a pre-trained uncertainty determination model to obtain the first leakage rate uncertainty. The present application does not limit the construction method and training process of the uncertainty determination model in any way.

[0105] In another alternative embodiment, exemplarily, the first leakage rate uncertainty may be determined by the following formula:

[0106] ;

[0107] In the formula, Q represents the first leakage rate uncertainty; V0 represents the container volume uncertainty corresponding to the earlier time in two adjacent times; V1 represents the container volume uncertainty corresponding to the later time in two adjacent times; t represents the time difference between the two adjacent times.

[0108] S402, determine the second leakage rate uncertainty according to the container volume uncertainty at two adjacent times.

[0109] Among them, the second leakage rate uncertainty characterizes the measurement uncertainty of the primary loop of the pressurized water reactor nuclear power plant, that is, the distinguishable leakage rate uncertainty.

[0110] Exemplarily, the second leakage rate uncertainty may be determined by the following formula:

[0111] ;

[0112] In the formula, Q i represents the uncertainty of the second leakage rate; W0 represents the uncertainty of the container volume corresponding to the previous moment among two adjacent moments; W1 represents the uncertainty of the container volume corresponding to the subsequent moment among two adjacent moments.

[0113] S403. Determine the uncertainty of the third leakage rate according to the uncertainty of the first leakage rate and the uncertainty of the container volume at the previous moment among two adjacent moments.

[0114] Among them, the uncertainty of the third leakage rate characterizes the prediction uncertainty of the primary loop of a pressurized water reactor nuclear power plant, that is, the uncertainty of the leakage rate that cannot be identified.

[0115] Exemplarily, the uncertainty of the third leakage rate can be determined by the following formula:

[0116] ;

[0117] In the formula, Q n represents the uncertainty of the third leakage rate; Q represents the uncertainty of the first leakage rate; W0 represents the uncertainty of the container volume corresponding to the previous moment among two adjacent moments.

[0118] In the above embodiments, when determining the uncertainty of the leakage rate, not only the overall uncertainty is considered, but also the distinguishable uncertainty and the indistinguishable uncertainty can be determined, that is, the uncertainty of the leakage rate is determined from multiple dimensions, making the accuracy of the uncertainty of the leakage rate higher.

[0119] To facilitate those skilled in the art to understand the present solution, in one embodiment, as Figure 5 shown, the method of the embodiment of the present application is introduced in detail, including the following steps:

[0120] S501. Obtain the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent moments.

[0121] Among them, the uncertainty influence parameters include the uncertainty of the container volume and the uncertainty of the container capacity.

[0122] Specifically, for each of the two adjacent moments, its uncertainty influence parameter is determined in the following manner:

[0123] First, obtain the primary loop environmental data at this moment and the preset primary loop environmental uncertainty; according to the pressure uncertainty, correct the pressure data at this moment to obtain the corrected pressure data at this moment; and, according to the temperature uncertainty, correct the temperature data at this moment to obtain the corrected temperature data at this moment. Determine the different density data corresponding to different primary loop environmental data of the liquid in the container at this moment according to the pressure data, corrected pressure data, temperature data, corrected temperature data, and liquid state data. Among them, the liquid state data includes the liquid mass and liquid volume of the liquid in the container.

[0124] Secondly, obtain the primary loop environmental uncertainty at this moment; among them, the primary loop environmental uncertainty includes the uncertainty of the volume control tank liquid level, the uncertainty of the relief tank liquid level, the uncertainty of the safety injection tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the sump buffer tank liquid level, and the uncertainty of the leakage measurement container liquid level. Determine the first change rate and the second change rate of the primary loop of the pressurized water reactor nuclear power plant at this moment according to each density data, pressure uncertainty, and temperature uncertainty. Among them, the first change rate characterizes the change rate of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to temperature change; the second change rate characterizes the change rate of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to pressure change.

[0125] Furthermore, determine the fluid mass uncertainty of the primary loop of the pressurized water reactor nuclear power plant at this moment according to the first change rate, the second change rate, temperature uncertainty, and pressure uncertainty; determine the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at this moment according to the fluid mass uncertainty and each density data; determine the container volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at this moment according to the fluid volume uncertainty and the volume control tank liquid level uncertainty; determine the container volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at this moment according to the uncertainty of the safety injection tank liquid level, the uncertainty of the relief tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the sump buffer tank liquid level, and the uncertainty of the leakage measurement container liquid level.

[0126] S502, determine the first leakage rate uncertainty according to the container volume uncertainty at two adjacent moments and the time difference between the two adjacent moments.

[0127] S503, determine the second leakage rate uncertainty according to the container volume uncertainty at two adjacent moments.

[0128] S504, determine the third leakage rate uncertainty according to the first leakage rate uncertainty and the container volume uncertainty at the earlier moment among the two adjacent moments.

[0129] Among them, the first leakage rate uncertainty characterizes the overall uncertainty of the primary loop of a pressurized water reactor nuclear power plant; the second leakage rate uncertainty characterizes the measurement uncertainty of the primary loop of a pressurized water reactor nuclear power plant; the third leakage rate uncertainty characterizes the measurement uncertainty of the primary loop of a pressurized water reactor nuclear power plant.

[0130] It should be understood that although the steps in the flowcharts involved in the above-described embodiments are shown in sequence according to the indications of the arrows, these steps are not necessarily executed in the order indicated by the arrows. Unless there is a clear description in this article, the execution of these steps has no strict order limit, and these steps can be executed in other orders. Moreover, at least a part of the steps in the flowcharts involved in the above-described embodiments may include multiple steps or multiple stages. These steps or stages are not necessarily executed at the same moment, but can be executed at different moments. The execution order of these steps or stages is not necessarily sequential, but can be executed alternately or in turn with at least a part of the steps or stages in other steps or other steps.

[0131] Based on the same inventive concept, an embodiment of the present application also provides a device for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant for implementing the method for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant involved above. The solution provided by this device for solving problems is similar to the solution described in the above method. Therefore, the specific limitations in one or more embodiments of the device for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant provided below can refer to the limitations on the method for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant in the above text, and will not be repeated here.

[0132] In one embodiment, as Figure 6 shown, a device for monitoring the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant is provided, including: an influence parameter determination module 610, a data acquisition module 620, and an uncertainty determination module 630, where:

[0133] The influence parameter determination module 610 is configured to determine the uncertainty influence parameter at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding moment.

[0134] The data acquisition module 620 is configured to acquire the uncertainty influence parameters of the primary loop of the pressurized water reactor nuclear power plant at two adjacent moments.

[0135] The uncertainty determination module 630 is configured to determine the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later moment among two adjacent moments according to the uncertainty influence parameters at two adjacent moments.

[0136] Among them, the uncertainty influence parameter includes at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of a pressurized water reactor nuclear power plant.

[0137] In one embodiment, the influence parameter determination module includes a first determination unit configured to, for each of two adjacent moments, determine the density data of the liquid in the target container at the moment according to the liquid state data of the target container at the moment; the liquid state data includes the liquid mass and the liquid volume of the liquid in the target container; and a second determination unit configured to determine the uncertainty influence parameter of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the density data.

[0138] In one embodiment, the first determination unit includes a data acquisition subunit configured to acquire the primary loop environment data and the preset primary loop environment uncertainty at the moment; and a first determination subunit configured to determine the density data of the liquid in the target container at the moment according to the liquid state data of the target container at the moment, the primary loop environment data, and the primary loop environment uncertainty.

[0139] In one embodiment, the first determination subunit is specifically configured to correct the pressure data at the moment according to the pressure uncertainty to obtain the corrected pressure data at the moment; and correct the temperature data at the moment according to the temperature uncertainty to obtain the corrected temperature data at the moment; and determine the different density data corresponding to different primary loop environment data of the liquid in the target container at the moment according to the pressure data, the corrected pressure data, the temperature data, the corrected temperature data, and the liquid state data.

[0140] In one embodiment, the influence parameter determination module includes a data acquisition unit configured to acquire the primary loop environment uncertainty at the moment; where the primary loop environment uncertainty includes the volume control tank liquid level uncertainty, the relief tank liquid level uncertainty, the safety injection tank liquid level uncertainty, the drain tank liquid level uncertainty, the sump buffer tank liquid level uncertainty, and the leak-off measurement container liquid level uncertainty; a third determination unit configured to determine the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant according to the density data, the temperature uncertainty, and the pressure uncertainty; a fourth determination unit configured to determine the container volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the fluid volume uncertainty and the volume control tank liquid level uncertainty; and a fifth determination unit configured to determine the container capacity uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the safety injection tank liquid level uncertainty, the relief tank liquid level uncertainty, the drain tank liquid level uncertainty, the sump buffer tank liquid level uncertainty, and the leak-off measurement container liquid level uncertainty.

[0141] In one embodiment, the third determination unit includes a second determination subunit, configured to determine a first change rate and a second change rate of the primary loop of a pressurized water reactor nuclear power plant at a moment according to respective density data, pressure uncertainty, and temperature uncertainty; wherein, the first change rate represents the change rate of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to temperature change; the second change rate represents the change rate of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to pressure change; a third determination subunit, configured to determine the fluid mass uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the first change rate, the second change rate, temperature uncertainty, and pressure uncertainty; a fourth determination subunit, configured to determine the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the fluid mass uncertainty and respective density data.

[0142] In one embodiment, the uncertainty determination module includes a sixth determination unit, configured to determine a first leakage rate uncertainty according to the container volume uncertainty at two adjacent moments and the time difference between the two adjacent moments; a seventh determination unit, configured to determine a second leakage rate uncertainty according to the container volume uncertainty at two adjacent moments; an eighth determination unit, configured to determine a third leakage rate uncertainty according to the first leakage rate uncertainty and the container volume uncertainty at the earlier moment among the two adjacent moments.

[0143] Wherein, the first leakage rate uncertainty represents the overall uncertainty of the primary loop of the pressurized water reactor nuclear power plant; the second leakage rate uncertainty represents the measurement uncertainty of the primary loop of the pressurized water reactor nuclear power plant; the third leakage rate uncertainty represents the prediction uncertainty of the primary loop of the pressurized water reactor nuclear power plant.

[0144] Each module in the above-mentioned leakage rate uncertainty monitoring device for the primary loop of a pressurized water reactor nuclear power plant can be implemented in whole or in part by software, hardware, and their combination. Each of the above modules can be embedded in or independent of a processor in a computer device in the form of hardware, or stored in a memory in the computer device in the form of software, so as to facilitate the processor to call and execute the operations corresponding to each of the above modules.

[0145] In an exemplary embodiment, there is provided a computer device, which may be a terminal, and its internal structure diagram may be as Figure 7As shown in the figure. The computer device includes a processor, a memory, an input / output interface, a communication interface, a display unit, and an input device. Among them, the processor, the memory, and the input / output interface are connected through a system bus, and the communication interface, the display unit, and the input device are connected to the system bus through the input / output interface. Among them, the processor of the computer device is used to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and computer programs. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage medium. The input / output interface of the computer device is used to exchange information between the processor and external devices. The communication interface of the computer device is used to communicate with external terminals in a wired or wireless manner, and the wireless manner can be implemented through WIFI, a mobile cellular network, NFC (Near Field Communication), or other technologies. When the computer program is executed by the processor, it implements a method for monitoring the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant. The display unit of the computer device is used to form a visually visible picture, which can be a display screen, a projection device, or a virtual reality imaging device. The display screen can be a liquid crystal display screen or an electronic ink display screen. The input device of the computer device can be a touch layer covering the display screen, or a button, a trackball, or a touchpad provided on the housing of the computer device, or an external keyboard, touchpad, or mouse, etc.

[0146] Those skilled in the art can understand that Figure 7 the structure shown in the figure is only a block diagram of some structures related to the solution of this application, and does not constitute a limitation on the computer device to which the solution of this application is applied. The specific computer device may include more or fewer components than those shown in the figure, or combine some components, or have different component arrangements.

[0147] In an exemplary embodiment, a computer device is provided, including a memory and a processor. A computer program is stored in the memory. When the processor executes the computer program, the following steps are implemented:

[0148] Obtain the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent times;

[0149] According to the uncertainty influence parameters at two adjacent times, determine the leakage rate uncertainty of the primary loop of a pressurized water reactor nuclear power plant at the later time among the two adjacent times; among them, the uncertainty influence parameters include at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of a pressurized water reactor nuclear power plant;

[0150] Among them, the uncertainty influence parameters at each time are obtained by the following method:

[0151] Determine the uncertainty influence parameter at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of a pressurized water reactor nuclear power plant at the corresponding moment.

[0152] In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored. When the computer program is executed by a processor, the following steps are implemented:

[0153] Obtain the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent moments;

[0154] Determine the leakage rate uncertainty at the later moment among two adjacent moments of the primary loop of a pressurized water reactor nuclear power plant according to the uncertainty influence parameters at two adjacent moments; wherein, the uncertainty influence parameter includes at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of a pressurized water reactor nuclear power plant;

[0155] Among them, the uncertainty influence parameter at each moment is obtained by the following method:

[0156] Determine the uncertainty influence parameter at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of a pressurized water reactor nuclear power plant at the corresponding moment.

[0157] In one embodiment, a computer program product is provided, including a computer program. When the computer program is executed by a processor, the following steps are implemented:

[0158] Obtain the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent moments;

[0159] Determine the leakage rate uncertainty at the later moment among two adjacent moments of the primary loop of a pressurized water reactor nuclear power plant according to the uncertainty influence parameters at two adjacent moments; wherein, the uncertainty influence parameter includes at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of a pressurized water reactor nuclear power plant;

[0160] Among them, the uncertainty influence parameter at each moment is obtained by the following method:

[0161] Determine the uncertainty influence parameter at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of a pressurized water reactor nuclear power plant at the corresponding moment.

[0162] Those of ordinary skill in the art can understand that all or part of the processes in the methods of the above embodiments can be completed by instructing relevant hardware through a computer program. The computer program can be stored in a non-volatile computer-readable storage medium. When the computer program is executed, it can include the processes of the embodiments of the above methods. Among them, any reference to a memory, database, or other medium used in the embodiments provided in the present application can include at least one of non-volatile and volatile memories. Non-volatile memory can include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetoresistive random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory can include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can be in various forms, such as static random access memory (SRAM) or dynamic random access memory (DRAM), etc. The databases involved in the embodiments provided in the present application can include at least one of relational databases and non-relational databases. Non-relational databases can include distributed databases based on blockchain, etc., without limitation. The processors involved in the embodiments provided in the present application can be general-purpose processors, central processors, graphics processors, digital signal processors, programmable logic devices, data processing logics based on quantum computing, etc., without limitation.

[0163] The technical features of the above embodiments can be combined arbitrarily. For the sake of brevity of description, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, it should be considered as the scope recorded in this specification.

[0164] The above-described embodiments merely represent several implementation manners of the present application. Their descriptions are relatively specific and detailed, but they should not be construed as limiting the patent scope of the present application. It should be noted that for those of ordinary skill in the art, without departing from the concept of the present application, several modifications and improvements can still be made, and these all belong to the protection scope of the present application. Therefore, the protection scope of the present application should be subject to the appended claims.

Claims

1. A monitoring method for the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant, characterized in that, The method includes: Obtaining the uncertainty influence parameters of the primary loop of a pressurized water reactor nuclear power plant at two adjacent moments; Determining the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later moment among the two adjacent moments according to the uncertainty influence parameters at the two adjacent moments; wherein, the uncertainty influence parameters include at least one of the container volume uncertainty and the container volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant; Among them, the uncertainty influence parameters at each moment are obtained in the following manner: Determining the uncertainty influence parameters at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding moment.

2. The method according to claim 1, characterized in that, The determining the uncertainty influence parameters at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding moment includes: For each of the two adjacent moments, determining the density data of the liquid in the target container at the moment according to the liquid state data of the target container at the moment; the liquid state data includes the liquid mass and the liquid volume of the liquid in the target container; Determining the uncertainty influence parameters of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the density data.

3. The method according to claim 2, wherein The determining the density data of the liquid in the target container at the moment according to the liquid state data of the target container at the moment includes: Obtaining the primary loop environment data at the moment and the preset primary loop environment uncertainty; Determining the density data of the liquid in the target container at the moment according to the liquid state data of the target container at the moment, the primary loop environment data, and the primary loop environment uncertainty.

4. The method according to claim 3, characterized in that, The primary loop environment data includes the pressure data and the temperature data of the primary loop of the pressurized water reactor nuclear power plant. Correspondingly, the primary loop environment uncertainty includes the temperature uncertainty and the pressure uncertainty; the determining the density data of the liquid in the target container at the moment according to the liquid state data of the target container at the moment, the primary loop environment data, and the primary loop environment uncertainty includes: Correcting the pressure data at the moment according to the pressure uncertainty to obtain the corrected pressure data at the moment; and, Correcting the temperature data at the moment according to the temperature uncertainty to obtain the corrected temperature data at the moment; Determining the different density data corresponding to different primary loop environment data of the liquid in the target container at the moment according to the pressure data, the corrected pressure data, the temperature data, the corrected temperature data, and the liquid state data.

5. The method according to claim 4, wherein The determining the uncertainty influence parameters of the target container at the moment according to the density data includes: Obtaining the primary loop environment uncertainty at the moment; wherein, the primary loop environment uncertainty includes the volume control tank liquid level uncertainty, the relief tank liquid level uncertainty, the safety injection tank liquid level uncertainty, the drain tank liquid level uncertainty, the sump buffer tank liquid level uncertainty, and the leakage measurement container liquid level uncertainty; Determine the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant according to each of the density data, the temperature uncertainty, and the pressure uncertainty; Determine the vessel volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the fluid volume uncertainty and the volume control tank liquid level uncertainty; Determine the vessel volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the accumulator tank liquid level uncertainty, the relief tank liquid level uncertainty, the drain tank liquid level uncertainty, the sump buffer tank liquid level uncertainty, and the letdown measurement vessel liquid level uncertainty; 6. The method according to claim 5, characterized in that The determining the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant according to each of the density data, the temperature uncertainty, and the pressure uncertainty includes: Determine the first change rate and the second change rate of the primary loop of the pressurized water reactor nuclear power plant at the moment according to each of the density data, the pressure uncertainty, and the temperature uncertainty; wherein, the first change rate characterizes the change rate of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to temperature change; the second change rate characterizes the change rate of the fluid density corresponding to the primary loop of the pressurized water reactor nuclear power plant with respect to pressure change; Determine the fluid mass uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the first change rate, the second change rate, the temperature uncertainty, and the pressure uncertainty; Determine the fluid volume uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the moment according to the fluid mass uncertainty and each of the density data; 7. The method according to any one of claims 1 to 6, characterized in that, The leakage rate uncertainty includes a first leakage rate uncertainty, a second leakage rate uncertainty, and a third leakage rate uncertainty; wherein, the first leakage rate uncertainty characterizes the overall leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant; the second leakage rate uncertainty characterizes the measurement uncertainty of the primary loop of the pressurized water reactor nuclear power plant; the third leakage rate uncertainty characterizes the prediction uncertainty of the primary loop of the pressurized water reactor nuclear power plant; the determining the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later moment among the adjacent two moments according to the uncertainty influence parameters at the adjacent two moments includes: Determine the first leakage rate uncertainty according to the vessel volume uncertainty at the adjacent two moments and the time difference between the adjacent two moments; Determine the second leakage rate uncertainty according to the vessel volume uncertainty at the adjacent two moments; Determine the third leakage rate uncertainty according to the first leakage rate uncertainty and the vessel volume uncertainty at the earlier moment among the adjacent two moments; 8. A monitoring device for the uncertainty of the primary loop leakage rate of a pressurized water reactor nuclear power plant, characterized in that, The device includes: A data acquisition module, which acquires the uncertainty influence parameters of the primary loop of the pressurized water reactor nuclear power plant at adjacent two moments; An uncertainty determination module determines the leakage rate uncertainty of the primary loop of the pressurized water reactor nuclear power plant at the later moment among the adjacent two moments according to the uncertainty influence parameters at the adjacent two moments; wherein, the uncertainty influence parameters include at least one of the container volume uncertainty and the container capacity uncertainty of the primary loop of the pressurized water reactor nuclear power plant; Wherein, the uncertainty influence parameters at each moment are obtained by the following method: An influence parameter determination module determines the uncertainty influence parameters at the corresponding moment according to the liquid state data corresponding to the target container in the primary loop of the pressurized water reactor nuclear power plant at the corresponding moment.

9. A computer device, comprising a memory and a processor, the memory storing a computer program, characterized in that, When the processor executes the computer program, the steps of the method described in any one of claims 1 to 7 are implemented.

10. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by the processor, the steps of the method described in any one of claims 1 to 7 are implemented.

11. A computer program product comprising a computer program, characterized in that, When the computer program is executed by the processor, the steps of the method described in any one of claims 1 to 7 are implemented.

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