Method and device for monitoring uncertainty of leakage rate of primary circuit of pressurized water reactor nuclear power plant

Abstract

The present application relates to a method and device for monitoring the uncertainty of the leakage rate of a primary circuit of a pressurized water reactor nuclear power plant. The method comprises: acquiring uncertainty influence parameters of a primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments; and on the basis of the uncertainty influence parameters at the two adjacent moments, determining the uncertainty of the leakage rate of the primary circuit of the pressurized water reactor nuclear power plant at the later one of the two adjacent moments; wherein the uncertainty influence parameters comprise at least one of container size uncertainty and container volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant; wherein the uncertainty influence parameters at each moment are obtained in the following mode: determining the uncertainty influence parameters at the corresponding moment on the basis of corresponding liquid state data of a target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment. By using the method, the accuracy of the uncertainty of the leakage rate of the primary circuit of the pressurized water reactor nuclear power plant can be improved.

Description

Method and device for monitoring uncertainty of primary circuit leakage rate in pressurized water reactor nuclear power plant

[0001] This application claims priority to Chinese patent application number CN202410373368.6, filed on March 29, 2024, entitled “Method and device for monitoring uncertainty of leakage rate of primary circuit of pressurized water reactor nuclear power plant”, the entire text of which is hereby incorporated by reference. Technical Field

[0002] The present application relates to the field of nuclear power technology, and in particular to a method and device for monitoring the uncertainty of leakage rate in a primary circuit of a pressurized water reactor nuclear power plant. Background Art

[0003] In the nuclear power sector, the primary circuit of a PWR nuclear power plant is primarily responsible for ensuring the normal operation of the reactor and its systems. It works in conjunction with the secondary circuit to heat the PWR core. Therefore, the primary circuit of a PWR nuclear power plant plays a vital role in the operation of the nuclear reactor. To ensure the safe operation of the primary circuit of a PWR nuclear power plant, regular primary circuit coolant leakage rate tests are required to monitor the coolant leakage rate within the primary circuit.

[0004] However, coolant leak rate tests in related technologies typically first determine an initial leak rate based on collected data, then evaluate the initial leak rate based on a pre-set leak rate uncertainty to obtain a more accurate target leak rate. However, in actual operation, the leak rate uncertainty is not constant at different times. Therefore, to improve the accuracy of the target leak rate, real-time monitoring of the leak rate uncertainty is necessary.

[0005] Summary of the Invention

[0006] Based on this, it is necessary to provide a method, device and product for monitoring the uncertainty of the primary circuit leakage rate of a pressurized water reactor nuclear power plant, which can improve the accuracy of the uncertainty of the leakage rate, in order to address the above technical problems.

[0007] In a first aspect, the present application provides a method for monitoring the uncertainty of leakage rate of a primary circuit of a pressurized water reactor nuclear power plant, comprising:

[0008] Obtain the uncertainty influencing parameters of the primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments;

[0009] determining, based on uncertainty influencing parameters at two adjacent moments, a leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at a later moment of the two adjacent moments; wherein the uncertainty influencing parameters include at least one of a volume uncertainty of a container and a capacity uncertainty of a container of the primary circuit of the pressurized water reactor nuclear power plant;

[0010] Among them, the uncertainty influencing parameters at each moment are obtained in the following way:

[0011] According to the liquid state data of the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameters at the corresponding moment are determined.

[0012] In one embodiment, based on the liquid state data corresponding to the target container in the primary circuit of a pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameter at the corresponding moment is determined, including: for each of two adjacent moments, based on the liquid state data of the target container at the moment, determining the density data of the liquid in the target container at the moment; the liquid state data includes the liquid mass and liquid volume of the liquid in the target container; based on the density data, determining the uncertainty influencing parameter of the primary circuit of the pressurized water reactor nuclear power plant at the moment.

[0013] In one embodiment, density data of the liquid in the target container at a moment is determined based on liquid state data of the target container at the moment, including: obtaining primary-loop environmental data and a preset primary-loop environmental uncertainty at the moment; and determining density data of the liquid in the target container at the moment based on the liquid state data of the target container at the moment, the primary-loop environmental data, and the primary-loop environmental uncertainty.

[0014] In one embodiment, the primary-loop environmental data includes pressure data and temperature data of the primary loop of a pressurized water reactor nuclear power plant, and correspondingly, the primary-loop environmental uncertainty includes temperature uncertainty and pressure uncertainty; based on the liquid state data of the target container at the time instant, the primary-loop environmental data and the primary-loop environmental uncertainty, the density data of the liquid in the target container at the time instant is determined, including: correcting the pressure data at the time instant according to the pressure uncertainty to obtain the corrected pressure data at the time instant; and correcting the temperature data at the time instant according to the temperature uncertainty to obtain the corrected temperature data at the time instant; determining different density data of the liquid in the target container at the time instant corresponding to different primary-loop environmental data according to the pressure data, the corrected pressure data, the temperature data, the corrected temperature data and the liquid state data.

[0015] In one embodiment, uncertainty influencing parameters of a target container at a time instant are determined based on density data, including: obtaining a primary circuit environmental uncertainty at the time instant; wherein the primary circuit environmental uncertainty includes the uncertainty of the liquid level of the control tank, the uncertainty of the liquid level of the pressure relief tank, the uncertainty of the liquid level of the injection tank, the uncertainty of the liquid level of the drain tank, the uncertainty of the liquid level of the pit buffer tank, and the uncertainty of the liquid level of the leakage measurement container; determining the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant based on the density data, temperature uncertainty, and pressure uncertainty; determining the container volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the time instant based on the fluid volume uncertainty and the uncertainty of the liquid level of the control tank; determining the container volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the time instant based on the uncertainty of the liquid level of the injection tank, the uncertainty of the liquid level of the pressure relief tank, the uncertainty of the liquid level of the drain tank, the uncertainty of the liquid level of the pit buffer tank, and the uncertainty of the liquid level of the leakage measurement container.

[0016] In one embodiment, the fluid volume uncertainty of a primary circuit of a pressurized water reactor nuclear power plant is determined based on various density data, temperature uncertainty, and pressure uncertainty, including: determining a first change rate and a second change rate of the primary circuit of the pressurized water reactor nuclear power plant at a time instant based on various density data, pressure uncertainty, and temperature uncertainty; wherein the first change rate represents the change rate of the fluid density corresponding to the primary circuit of the pressurized water reactor nuclear power plant with temperature change; the second change rate represents the change rate of the fluid density corresponding to the primary circuit of the pressurized water reactor nuclear power plant with pressure change; determining the fluid mass uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at a time instant based on the first change rate, the second change rate, the temperature uncertainty, and the pressure uncertainty; determining the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at a time instant based on the fluid mass uncertainty and various density data.

[0017] 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 characterizes the overall leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant; the second leakage rate uncertainty characterizes the measurement uncertainty of a primary circuit of a pressurized water reactor nuclear power plant; the third leakage rate uncertainty characterizes the prediction uncertainty of a primary circuit of a pressurized water reactor nuclear power plant; and the leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at a later moment in two adjacent moments is determined based on uncertainty influencing parameters at two adjacent moments, including: determining the first leakage rate uncertainty based on the uncertainty of the container volume at the two adjacent moments and the time difference between the two adjacent moments; determining the second leakage rate uncertainty based on the uncertainty of the container volume at the two adjacent moments; and determining the third leakage rate uncertainty based on the first leakage rate uncertainty and the uncertainty of the container volume at the earlier moment in two adjacent moments.

[0018] In a second aspect, the present application further provides a device for monitoring the uncertainty of leakage rate of a primary circuit of a pressurized water reactor nuclear power plant, comprising:

[0019] The data acquisition module obtains the uncertainty influencing parameters of the primary circuit of the pressurized water reactor nuclear power plant at two adjacent moments;

[0020] an uncertainty determination module, which determines the leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the later of two adjacent moments based on uncertainty influencing parameters at two adjacent moments; wherein the uncertainty influencing parameters include at least one of the uncertainty of the volume of the container and the uncertainty of the capacity of the container of the primary circuit of the pressurized water reactor nuclear power plant;

[0021] Among them, the uncertainty influencing parameters at each moment are obtained in the following way:

[0022] The influencing parameter determination module determines the uncertainty influencing parameters at a corresponding moment according to the liquid state data corresponding to the target container in the primary circuit of the pressurized water reactor nuclear power plant at a corresponding moment.

[0023] In a third aspect, the present application further provides a computer device comprising a memory and a processor, wherein the memory stores a computer program, and when the processor executes the computer program, the following steps are implemented:

[0024] Obtain the uncertainty influencing parameters of the primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments;

[0025] determining, based on uncertainty influencing parameters at two adjacent moments, a leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at a later moment of the two adjacent moments; wherein the uncertainty influencing parameters include at least one of a volume uncertainty of a container and a capacity uncertainty of a container of the primary circuit of the pressurized water reactor nuclear power plant;

[0026] Among them, the uncertainty influencing parameters at each moment are obtained in the following way:

[0027] According to the liquid state data of the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameters at the corresponding moment are determined.

[0028] In a fourth aspect, the present application further provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the following steps:

[0029] Obtain the uncertainty influencing parameters of the primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments;

[0030] determining, based on uncertainty influencing parameters at two adjacent moments, a leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at a later moment of the two adjacent moments; wherein the uncertainty influencing parameters include at least one of a volume uncertainty of a container and a capacity uncertainty of a container of the primary circuit of the pressurized water reactor nuclear power plant;

[0031] Among them, the uncertainty influencing parameters at each moment are obtained in the following way:

[0032] According to the liquid state data of the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameters at the corresponding moment are determined.

[0033] In a fifth aspect, the present application further provides a computer program product, comprising a computer program, which, when executed by a processor, implements the following steps:

[0034] Obtain the uncertainty influencing parameters of the primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments;

[0035] determining, based on uncertainty influencing parameters at two adjacent moments, a leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at a later moment of the two adjacent moments; wherein the uncertainty influencing parameters include at least one of a volume uncertainty of a container and a capacity uncertainty of a container of the primary circuit of the pressurized water reactor nuclear power plant;

[0036] Among them, the uncertainty influencing parameters at each moment are obtained in the following way:

[0037] According to the liquid state data of the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameters at the corresponding moment are determined.

[0038] The aforementioned method and device for monitoring the primary circuit leakage rate uncertainty of a pressurized water reactor nuclear power plant determines the leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the later of two adjacent moments in time based on the uncertainty influencing parameters of the primary circuit of the pressurized water reactor nuclear power plant at two adjacent moments in time. Because the uncertainty influencing parameters at different moments in time are determined based on the liquid state data corresponding to the target container of the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moments in time, the corresponding uncertainty influencing parameters at different moments in time are affected by the state of the liquid in the target container at the corresponding moments in time. In other words, the uncertainty influencing parameters can more accurately characterize the state of the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moments in time. Furthermore, the leakage rate uncertainty determined based on the uncertainty influencing parameters at two adjacent moments in time is also accurate. In other words, the aforementioned method not only monitors the leakage rate uncertainty of the primary circuit of a pressurized water reactor nuclear power plant in real time, but also ensures the accuracy of the leakage rate uncertainty. BRIEF DESCRIPTION OF THE DRAWINGS

[0039] In order to more clearly illustrate the technical solutions in the embodiments of the present application or related technologies, the following briefly introduces the drawings required for use in the embodiments or related technical descriptions. Obviously, the drawings described below are only some embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying any creative work.

[0040] FIG1 is an application diagram of a method for monitoring uncertainty of leakage rate of a primary circuit of a pressurized water reactor nuclear power plant provided by this embodiment;

[0041] FIG2 is a flow chart of a method for monitoring uncertainty of leakage rate of a primary circuit of a pressurized water reactor nuclear power plant provided by this embodiment;

[0042] FIG3 is a schematic diagram of a process for determining uncertainty influencing parameters provided by this embodiment;

[0043] FIG4 is a schematic diagram of a flow chart of determining the uncertainty of a leakage rate provided by this embodiment;

[0044] FIG5 is a flow chart of another method for monitoring the uncertainty of leakage rate in a primary circuit of a pressurized water reactor nuclear power plant provided by this embodiment;

[0045] FIG6 is a structural block diagram of a device for monitoring the uncertainty of leakage rate in a primary circuit of a pressurized water reactor nuclear power plant provided by this embodiment;

[0046] FIG7 is a diagram showing the internal structure of a computer device provided in this embodiment. DETAILED DESCRIPTION

[0047] In order to make the purpose, technical solutions and advantages of this application more clear, the following further describes this application in detail with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain this application and are not intended to limit this application.

[0048] Before introducing the embodiments of the present application, it should be noted that in the field of nuclear power technology, the reactor core generates huge heat energy due to the fission of nuclear fuel. 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-tube in the steam generator, and transfers the heat energy to the secondary circuit cooling water outside the U-tube through the tube wall. After releasing the heat, it is sent back to the core by the main pump for reheating and then enters the steam generator. The water circulates continuously in this closed loop, which is called a primary loop. The primary loop of a pressurized water reactor nuclear power plant plays a vital role in the combustion process of the nuclear reactor.

[0049] However, the primary circuit is radioactive. When a PWR suffers a small leak, radioactive materials in the reactor coolant could enter the containment vessel and potentially leak through it, contaminating the primary circuit environment. Furthermore, when an accident occurs, the sudden loss of coolant pressure at the leak site could generate a strong shock wave within the primary circuit system. This shock wave could damage the core structure and cause pipes to swing, further damaging the facilities within the containment. In other words, a serious leak in the primary circuit of a PWR nuclear power plant could result in a major accident. Therefore, personnel typically regularly calculate the leakage rate of the primary circuit of a PWR nuclear power plant to ensure it remains within a safe range.

[0050] In the process of determining the leakage rate of a primary circuit of a pressurized water reactor nuclear power plant, leakage rate uncertainty is usually introduced to calibrate the measured leakage rate of the primary circuit of the pressurized water reactor nuclear power plant. However, in traditional technologies, the leakage rate uncertainty is usually predetermined based on manual experience, and there are inaccuracies, which will lead to inaccurate leakage rate of the primary circuit of the pressurized water reactor nuclear power plant. In order to improve the accuracy of the leakage rate of the primary circuit of the pressurized water reactor nuclear power plant, an embodiment of the present application provides a method that can monitor the uncertainty of the leakage rate of the primary circuit of the pressurized water reactor nuclear power plant in real time, improve the accuracy of the uncertainty of the leakage rate of the primary circuit of the pressurized water reactor nuclear power plant, and thus achieve the purpose of improving the accuracy of the leakage rate of the primary circuit of the pressurized water reactor nuclear power plant.

[0051] The method for monitoring the uncertainty of leakage rate in the primary circuit of a pressurized water reactor nuclear power plant provided in an embodiment of the present application can be applied in the application environment shown in Figure 1. A terminal 102 communicates with a server 104 via a network. A data storage system can store data that server 104 needs to process. The data storage system can be integrated with server 104, or located in the cloud or on another network server. Specifically, server 104 obtains uncertainty influencing parameters of the primary circuit of the pressurized water reactor nuclear power plant at two adjacent moments in time. Based on the uncertainty influencing parameters at the two adjacent moments in time, server 104 determines the uncertainty of leakage rate in the primary circuit of the pressurized water reactor nuclear power plant at the later of the two adjacent moments in time. The leakage rate uncertainty is then displayed via terminal 102. The uncertainty influencing parameters include at least one of container volume uncertainty and container capacity uncertainty. The uncertainty influencing parameters at each moment in time are determined by server 104 based on the liquid state data corresponding to the target container in the primary circuit of the pressurized water reactor nuclear power plant at that moment in time. Terminal 102 may include, but is not limited to, various personal computers, laptops, smartphones, tablets, IoT devices, and portable wearable devices. IoT devices may include smart speakers, smart TVs, smart air conditioners, and smart car devices. Portable wearable devices may include smart watches, smart bracelets, and head-mounted devices. Server 104 may be implemented as a standalone server or a server cluster consisting of multiple servers.

[0052] In one embodiment, as shown in FIG2 , a method for monitoring the uncertainty of leakage rate in a primary circuit of a pressurized water reactor nuclear power plant is provided. The method is described by taking the server 104 in FIG1 as an example, and includes the following steps:

[0053] S201, obtaining uncertainty influencing parameters of a primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments.

[0054] The uncertainty influencing parameter at each moment represents a parameter that may affect the uncertainty of the leakage rate of the primary circuit of a pressurized water reactor nuclear power plant at that moment. Exemplarily, the uncertainty influencing parameter includes at least one of the uncertainty of the volume of the vessel in the primary circuit of the pressurized water reactor nuclear power plant and the uncertainty of the vessel capacity. The vessel in the primary circuit of the pressurized water reactor nuclear power plant represents the reactor pressure vessel in the primary circuit of the pressurized water reactor nuclear power plant. This embodiment of the present application does not limit the time difference between two adjacent moments.

[0055] For example, in this embodiment, between two adjacent moments in time, the uncertainty influencing parameters at the earlier moment have already been determined when determining the corresponding primary circuit leakage rate of a pressurized water reactor nuclear power plant. These parameters can be stored in a corresponding database and directly retrieved from the database when determining the primary circuit leakage rate of the pressurized water reactor nuclear power plant at the later moment. Between two adjacent moments in time, the uncertainty influencing parameters at the later moment can be determined by this server using the following method, or can be determined by a server associated with this server using the following method or other methods capable of determining uncertainty influencing parameters, without limitation.

[0056] In an optional embodiment, the uncertainty influencing parameters at different moments in two adjacent moments can be obtained in the following manner: the uncertainty influencing parameters at the corresponding moment are determined based on the liquid state data corresponding to the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment.

[0057] The liquid state data is used to represent the state data of the liquid in the reactor pressure vessel in the primary circuit of a pressurized water reactor nuclear power plant. For example, the liquid state data may represent at least one of the state data such as the temperature, volume and density of the liquid.

[0058] In an optional 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 impose any restrictions on the construction method and training process of the uncertainty influence parameter determination model.

[0059] S202 , determining the leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the later of the two adjacent moments according to the uncertainty influencing parameters at the two adjacent moments.

[0060] In an optional embodiment, the uncertainty influencing 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 circuit of the pressurized water reactor nuclear power plant at the later moment of the two adjacent moments.

[0061] In another optional embodiment, the uncertainty influencing parameters at two adjacent moments can be processed according to a predetermined leakage rate uncertainty determination formula to obtain the leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the later moment of the two adjacent moments.

[0062] It should be noted that the embodiments of this application do not impose any restrictions on the construction method and training process of the leakage rate uncertainty determination model. The uncertainty determination formula can be determined based on manual experience or through a large number of experiments, and there is no limitation on this.

[0063] In the aforementioned method for monitoring the primary circuit leakage rate uncertainty of a pressurized water reactor nuclear power plant, the leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the later of the two adjacent moments is determined based on the uncertainty influencing parameters of the primary circuit of the pressurized water reactor nuclear power plant at two adjacent moments. Because the uncertainty influencing parameters at different moments are determined based on the liquid state data corresponding to the target container of the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moments, the corresponding uncertainty influencing parameters at different moments are affected by the state of the liquid in the target container at the corresponding moments. In other words, the uncertainty influencing parameters can more accurately characterize the state of the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moments. Furthermore, the leakage rate uncertainty determined based on the uncertainty influencing parameters at two adjacent moments is also accurate. In other words, the aforementioned method not only monitors the leakage rate uncertainty of the primary circuit of a pressurized water reactor nuclear power plant in real time, but also ensures the accuracy of the leakage rate uncertainty.

[0064] On the basis of the above embodiments, in order to further improve the accuracy of the uncertainty influencing parameters at each moment, in one embodiment, a specific method for determining the uncertainty influencing parameters at different moments is provided, as shown in FIG3 , including the following steps:

[0065] S301 , for each of two adjacent moments, determining density data of the liquid in the target container at that moment according to the liquid state data of the target container at that moment.

[0066] The target container may be any container in the primary circuit of a pressurized water reactor nuclear power plant, for example, a control tank. The liquid state data includes the liquid mass and liquid volume of the liquid in the container.

[0067] In an optional embodiment, in this embodiment, the ratio of the liquid mass to the liquid volume of the liquid in the target container at that moment can be directly used as the density data of the liquid in the target container at that moment.

[0068] In another optional embodiment, in order to improve the accuracy of the density data of the liquid in the target container at different moments, the influence of the first-loop environmental uncertainty on the density data is introduced in the process of determining the density data. The first-loop environmental uncertainty includes temperature uncertainty and pressure uncertainty; accordingly, determining the density data of the liquid in the target container at that moment includes the following steps: obtaining the environmental data at that moment and the preset first-loop environmental uncertainty; determining the density data of the liquid in the target container at that moment based on the liquid state data of the target container at that moment, the first-loop environmental data and the first-loop environmental uncertainty. Among them, the first-loop environmental data can include at least one of the environmental data such as temperature data and pressure data in the first loop. The first-loop environmental uncertainty is used to characterize the uncertainty between the collected environmental data and the actual environmental data. The first-loop environmental uncertainty can be determined manually or obtained through a large number of experiments, and there is no limitation on this.

[0069] For example, in this embodiment, the primary circuit environment data of the container at a given moment can be acquired by a sensor, and the liquid state data, primary circuit environment data, and a preset primary circuit environment uncertainty at that moment can be input into a predetermined density data determination model to obtain the density data of the liquid in the target container at that moment. Alternatively, the liquid state data, primary circuit environment data, and a preset primary circuit environment uncertainty at that moment can be processed according to a predetermined density data determination formula to obtain the density data of the liquid in the target container at that moment.

[0070] It should be noted that the present embodiment does 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 through a large number of experiments, and there is no limitation on this.

[0071] In order to make the process of determining density data in this embodiment more detailed, the embodiment of the present application takes the example of a loop environment including pressure data and temperature data, and the uncertainty of the loop environment including temperature uncertainty and pressure uncertainty, and explains in detail the density data of the liquid in the target container at different moments: according to the pressure uncertainty, the pressure data at that moment is corrected to obtain the corrected pressure data at that moment; and according to the temperature uncertainty, the temperature data at that moment is corrected to obtain the corrected temperature data at that moment; according to the pressure data, corrected pressure data, temperature data, corrected temperature data and liquid state data, the different density data corresponding to the loop environment data of different containers at different moments in the target container are determined. Among them, the corrected pressure data represents the corrected pressure data. The corrected temperature data represents the corrected temperature data.

[0072] For example, the pressure data may be corrected based on the following formula: P' = P + B;

[0073] Where P' represents the corrected pressure data; P represents the pressure data; and B represents the pressure uncertainty.

[0074] The temperature data can be corrected based on the following formula: T'=T+A;

[0075] Where T' represents the corrected temperature data; T represents the temperature data; and A represents the temperature uncertainty.

[0076] Furthermore, in this embodiment, "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 input as input data into the density data determination model to obtain different density data corresponding to the three input data, such as ρ1, ρ2 and ρ3.

[0077] S302: Determine uncertainty influencing parameters of the primary circuit of the pressurized water reactor nuclear power plant at this moment based on the density data.

[0078] In an optional implementation, the density data may be input into a pre-trained uncertainty influencing parameter determination model to obtain the uncertainty influencing parameters of the primary circuit of the pressurized water reactor nuclear power plant at that moment.

[0079] In another optional embodiment, the following method can also be used for determination: obtaining the uncertainty of the primary circuit environment at that moment; wherein, the primary circuit environment uncertainty includes the uncertainty of the control tank liquid level, the uncertainty of the injection tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the pit buffer tank liquid level and the uncertainty of the leakage measurement container liquid level, and determining the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant according to the density data, temperature uncertainty and pressure uncertainty; determining the uncertainty of the container volume of the primary circuit of the pressurized water reactor nuclear power plant at that moment according to the fluid volume uncertainty and the uncertainty of the control tank liquid level; determining the uncertainty of the container volume of the primary circuit of the pressurized water reactor nuclear power plant at that moment according to the uncertainty of the injection tank liquid level, the uncertainty of the pressure relief tank liquid level, the uncertainty of the drain tank liquid level, the uncertainty of the pit buffer tank liquid level and the uncertainty of the leakage measurement container liquid level. Among them, the leakage measurement container can be the reactor pressure vessel O-ring leakage measurement container; the control box liquid level uncertainty, the injection box liquid level uncertainty, the drain tank liquid level uncertainty, the pit buffer tank liquid level uncertainty and the leakage measurement container liquid level uncertainty respectively represent the uncertainty of the collected data corresponding to other different liquid tanks except the target container.

[0080] In an optional embodiment, the density data, temperature uncertainty, and pressure uncertainty can be input into a predetermined liquid volume uncertainty determination model to obtain the liquid volume uncertainty of the primary circuit of a pressurized water reactor nuclear power plant. The fluid volume uncertainty and the control tank liquid level uncertainty are then input into a predetermined container volume uncertainty determination model to obtain the container volume uncertainty. Similarly, the injection tank liquid level uncertainty, the drain tank liquid level uncertainty, the pit buffer tank liquid level uncertainty, and the leakage measurement container liquid level uncertainty are input into a predetermined container volume uncertainty determination model to determine the container volume uncertainty. Each model can be a neural network model or a calculation formula. In the case where the model is a neural network model, the embodiment of the present application does not limit the construction method and training process of each model. In the case where the model is a calculation formula, the calculation formula can be determined based on manual experience or through a large number of experiments, and there is no limitation on this.

[0081] Furthermore, in another optional embodiment, the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant can be determined in the following manner: based on the density data, pressure uncertainty and temperature uncertainty, determine the first change rate and second change rate of the primary circuit of the pressurized water reactor nuclear power plant at the time instant; wherein the first change rate represents the change rate of the fluid density corresponding to the primary circuit of the pressurized water reactor nuclear power plant with temperature changes; the second change rate represents the change rate of the fluid density corresponding to the primary circuit of the pressurized water reactor nuclear power plant with pressure changes; based on the first change rate, the second change rate, the temperature uncertainty and the pressure uncertainty, determine the fluid mass uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at this moment; based on the fluid mass uncertainty and the density data, determine the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the time instant.

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

[0083] Where Δρ T Represents the first rate of change; ρ2 represents the density data determined by taking "pressure data P, corrected temperature data T' and liquid state data" as input data; ρ1 represents the density data determined by taking "pressure data P, temperature data T and liquid state data" as input data; A represents temperature uncertainty.

[0084] For example, the second change rate can be determined by the following formula:

[0085] Where Δρ PRepresents 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 pressure uncertainty.

[0086] For example, the uncertainty of the fluid quality in the primary circuit of a pressurized water reactor nuclear power plant at this moment can be determined by the following formula:

[0087] Where m L represents the uncertainty of the fluid quality in the primary circuit of a pressurized water reactor nuclear power plant at that moment; Δρ T represents the first rate of change; Δρ P represents the second rate of change; A represents the temperature uncertainty; B represents the pressure uncertainty.

[0088] For example, the uncertainty of the fluid volume in the primary circuit of a pressurized water reactor nuclear power plant at time instant can be determined by the following formula:

[0089] Where V L represents the uncertainty of the fluid volume in the primary circuit of a pressurized water reactor nuclear power plant at that moment; m L It represents the uncertainty of fluid quality in the primary circuit of a pressurized water reactor nuclear power plant at that moment.

[0090] Furthermore, the uncertainty of the container volume of the primary circuit of the pressurized water reactor nuclear power plant at this moment can be determined by the following formula:

[0091] Where V represents the uncertainty of the container volume of the primary circuit of the pressurized water reactor nuclear power plant at this moment; V L It represents the uncertainty of the fluid volume in the primary circuit of the pressurized water reactor nuclear power plant at that moment; C represents the uncertainty of the liquid level in the control tank.

[0092] For example, the uncertainty of the container volume of the primary circuit of a pressurized water reactor nuclear power plant at this moment can be determined by the following formula:

[0093] Where W represents the uncertainty of the container volume of the primary circuit of the pressurized water reactor nuclear power plant at that moment; D represents the uncertainty of the pressure relief tank liquid level; E represents the uncertainty of the injection tank liquid level; F represents the uncertainty of the drain tank liquid level; G represents the uncertainty of the pit buffer tank liquid level; and H represents the uncertainty of the leakage measurement container liquid level.

[0094] In the above embodiment, in the process of determining the density data of the liquid in the container at different times, the influence of the primary circuit environmental data and the primary circuit environmental uncertainty on the density data is taken into consideration, so that the determined density data is more accurate, and thus the uncertainty influence parameters of the primary circuit of the pressurized water reactor nuclear power plant at two adjacent times determined based on the density data are more accurate.

[0095] Based on 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. Accordingly, as shown in FIG4 , a method for determining the leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at the later of two adjacent moments may include the following steps:

[0096] S401 : Determine a first leakage rate uncertainty according to the uncertainty of the container volume at two adjacent moments and the time difference between the two adjacent moments.

[0097] The first leakage rate uncertainty represents the overall uncertainty of the primary circuit of the pressurized water reactor nuclear power plant, that is, the total uncertainty of the leakage rate.

[0098] In an optional embodiment, the uncertainty of the container volume at two adjacent moments and the time difference between the two adjacent moments can be input into a pre-trained uncertainty determination model to obtain the first leakage rate uncertainty. This embodiment of the present application does not impose any restrictions on the construction method and training process of the uncertainty determination model.

[0099] In another optional embodiment, illustratively, the first leakage rate uncertainty may be determined by the following formula:

[0100] Where Q represents the uncertainty of the first leakage rate; V0 represents the uncertainty of the container volume corresponding to the earlier of two adjacent moments; V1 represents the uncertainty of the container volume corresponding to the later of two adjacent moments; and t represents the time difference between the two adjacent moments.

[0101] S402: Determine a second leakage rate uncertainty based on the container volume uncertainty at two adjacent moments.

[0102] Among them, the second leakage rate uncertainty represents the measurement uncertainty of the primary circuit of the pressurized water reactor nuclear power plant, that is, the identifiable leakage rate uncertainty.

[0103] For example, the second leakage rate uncertainty can be determined by the following formula:

[0104] Where Qi represents the uncertainty of the second leakage rate; W0 represents the uncertainty of the container volume corresponding to the earlier moment in two adjacent moments; and W1 represents the uncertainty of the container volume corresponding to the later moment in two adjacent moments.

[0105] S403: Determine a third leakage rate uncertainty according to the first leakage rate uncertainty and the container volume uncertainty at the previous moment in two adjacent moments.

[0106] Among them, the third leakage rate uncertainty characterizes the prediction uncertainty of the primary circuit of the pressurized water reactor nuclear power plant, that is, the unidentifiable leakage rate uncertainty.

[0107] Exemplarily, the third leak rate uncertainty can be determined by the following formula: Q n =Q-W0;

[0108] Where Qn represents the third leakage rate uncertainty; Q represents the first leakage rate uncertainty; and W0 represents the container volume uncertainty corresponding to the previous moment in two adjacent moments.

[0109] In the above embodiment, when determining the leakage rate uncertainty, not only the overall uncertainty is considered, but also the identifiable uncertainty and the unidentifiable uncertainty can be determined, that is, the leakage rate uncertainty is determined from multiple dimensions, so that the accuracy of the leakage rate uncertainty is higher.

[0110] To facilitate those skilled in the art to understand the present solution, in one embodiment, as shown in FIG5 , the method of the embodiment of the present application is described in detail, including the following steps:

[0111] S501, obtaining uncertainty influencing parameters of a primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments.

[0112] Among them, the uncertainty influencing parameters include container volume uncertainty and container capacity uncertainty.

[0113] Specifically, for each of two adjacent moments, the uncertainty influencing parameters are determined in the following way:

[0114] First, the primary circuit environmental data at that moment and the preset primary circuit environmental uncertainty are obtained. The pressure data at that moment is corrected based on the pressure uncertainty to obtain the corrected pressure data at that moment. Furthermore, the temperature data at that moment is corrected based on the temperature uncertainty to obtain the corrected temperature data at that moment. Based on the pressure data, corrected pressure data, temperature data, corrected temperature data, and liquid state data, the different density data corresponding to the primary circuit environmental data of different containers at that moment are determined. The liquid state data includes the liquid mass and liquid volume of the liquid in the container.

[0115] Next, the primary circuit environmental uncertainty at that moment is determined. This includes the uncertainty of the control tank level, the pressure relief tank level, the injection tank level, the drain tank level, the pit buffer tank level, and the leak measurement vessel level. Based on the density data, pressure uncertainty, and temperature uncertainty, the first and second rates of change of the primary circuit of the PWR nuclear power plant at that moment are determined. The first rate of change represents the rate of change of the fluid density in the primary circuit of the PWR nuclear power plant with temperature changes, while the second rate of change represents the rate of change of the fluid density in the primary circuit of the PWR nuclear power plant with pressure changes.

[0116] Furthermore, based on the first change rate, the second change rate, the temperature uncertainty and the pressure uncertainty, the fluid mass uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at this moment is determined; based on the fluid mass uncertainty and the density data, the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at this moment is determined; based on the fluid volume uncertainty and the control tank liquid level uncertainty, the container volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at this moment is determined; based on the injection tank liquid level uncertainty, the pressure relief tank liquid level uncertainty, the drain tank liquid level uncertainty, the pit buffer tank liquid level uncertainty and the leakage measurement container liquid level uncertainty, the container volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at this moment is determined.

[0117] S502: Determine a first leakage rate uncertainty according to the uncertainty of the container volume at two adjacent moments and the time difference between the two adjacent moments.

[0118] S503: Determine a second leakage rate uncertainty based on the container volume uncertainty at two adjacent moments.

[0119] S504: Determine a third leakage rate uncertainty based on the first leakage rate uncertainty and the container volume uncertainty at the previous moment in two adjacent moments.

[0120] Among them, the first leakage rate uncertainty characterizes the overall uncertainty of the primary circuit of the pressurized water reactor nuclear power plant; the second leakage rate uncertainty characterizes the measurement uncertainty of the primary circuit of the pressurized water reactor nuclear power plant; and the third leakage rate uncertainty characterizes the measurement uncertainty of the primary circuit of the pressurized water reactor nuclear power plant.

[0121] It should be understood that, although the various steps in the flowcharts involved in the various embodiments described above are displayed in sequence according to the instructions of the arrows, these steps are not necessarily executed in sequence in the order indicated by the arrows. Unless otherwise specified herein, there is no strict order restriction on the execution of these steps, and these steps can be executed in other orders. Moreover, at least a portion of the steps in the flowcharts involved in the various embodiments described above can include multiple steps or multiple stages, and these steps or stages are not necessarily executed and completed at the same time, but can be executed at different times, and the execution order of these steps or stages is not necessarily to be carried out in sequence, but can be executed in turn or alternately with other steps or at least a portion of steps or stages in other steps.

[0122] Based on the same inventive concept, embodiments of the present application also provide a pressurized water reactor nuclear power plant primary circuit leakage rate uncertainty monitoring device for implementing the aforementioned pressurized water reactor nuclear power plant primary circuit leakage rate uncertainty monitoring method. The solution provided by this device is similar to the solution described in the aforementioned method. Therefore, the specific limitations of one or more embodiments of the pressurized water reactor nuclear power plant primary circuit leakage rate uncertainty monitoring device provided below can be found in the limitations of the pressurized water reactor nuclear power plant primary circuit leakage rate uncertainty monitoring method described above and will not be repeated here.

[0123] In one embodiment, as shown in FIG6 , a device for monitoring the uncertainty of leakage rate of a primary circuit of a pressurized water reactor nuclear power plant is provided, comprising: an influencing parameter determination module 610 , a data acquisition module 620 , and an uncertainty determination module 630 , wherein:

[0124] The influencing parameter determination module 610 is used to determine the uncertainty influencing parameter at a corresponding moment according to the liquid state data corresponding to the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment.

[0125] The data acquisition module 620 is used to obtain uncertainty influencing parameters of the primary circuit of the pressurized water reactor nuclear power plant at two adjacent moments.

[0126] The uncertainty determination module 630 is used to determine the leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the later moment of two adjacent moments according to the uncertainty influencing parameters at two adjacent moments.

[0127] The uncertainty influencing parameter includes at least one of a volume uncertainty of a container and a capacity uncertainty of a container in a primary circuit of a pressurized water reactor nuclear power plant.

[0128] In one embodiment, the influencing parameter determination module includes a first determination unit, which is used to determine, for each of two adjacent moments, the density data of the liquid in the target container at a moment in time based on the liquid state data of the target container at the moment in time; the liquid state data includes the liquid mass and liquid volume of the liquid in the target container; and a second determination unit, which is used to determine the uncertainty influencing parameter of the primary circuit of the pressurized water reactor nuclear power plant at a moment in time based on the density data.

[0129] In one embodiment, the first determination unit includes a data acquisition subunit, which is used to obtain the first-loop environmental data at a moment and a preset first-loop environmental uncertainty; the first determination subunit is used to determine the density data of the liquid in the target container at a moment based on the liquid state data of the target container at a moment, the first-loop environmental data and the first-loop environmental uncertainty.

[0130] In one embodiment, the first determination subunit is specifically used to correct the pressure data at the moment according to the pressure uncertainty to obtain the corrected pressure data at the moment; and to correct the temperature data at the moment according to the temperature uncertainty to obtain the corrected temperature data at the moment; and to determine the different density data corresponding to the different circuit environmental 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.

[0131] In one embodiment, the influencing parameter determination module includes a data acquisition unit for acquiring the uncertainty of the primary circuit environment at a moment in time; wherein, the primary circuit environment uncertainty includes the uncertainty of the liquid level of the control tank, the uncertainty of the liquid level of the pressure relief tank, the uncertainty of the liquid level of the injection tank, the uncertainty of the liquid level of the drain tank, the uncertainty of the liquid level of the pit buffer tank and the uncertainty of the liquid level of the leakage measurement container; a third determination unit for determining the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant according to various density data, temperature uncertainty and pressure uncertainty; a fourth determination unit for determining the container volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at a moment in time according to the fluid volume uncertainty and the liquid level uncertainty of the control tank; a fifth determination unit for determining the container volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at a moment in time according to the uncertainty of the liquid level of the injection tank, the uncertainty of the liquid level of the pressure relief tank, the uncertainty of the liquid level of the drain tank, the uncertainty of the liquid level of the pit buffer tank and the uncertainty of the liquid level of the leakage measurement container.

[0132] In one embodiment, the third determination unit includes a second determination subunit, which is used to determine the first change rate and the second change rate of the primary circuit of the pressurized water reactor nuclear power plant at the time instant based on the density data, pressure uncertainty and temperature uncertainty; wherein the first change rate represents the change rate of the fluid density corresponding to the primary circuit of the pressurized water reactor nuclear power plant with the change of temperature; the second change rate represents the change rate of the fluid density corresponding to the primary circuit of the pressurized water reactor nuclear power plant with the change of pressure; the third determination subunit is used to determine the fluid mass uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the time instant based on the first change rate, the second change rate, the temperature uncertainty and the pressure uncertainty; the fourth determination subunit is used to determine the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the time instant based on the fluid mass uncertainty and the density data.

[0133] In one embodiment, the uncertainty determination module includes a sixth determination unit for determining a first leakage rate uncertainty based on the uncertainty of the container volume at two adjacent moments and the time difference between the two adjacent moments; a seventh determination unit for determining a second leakage rate uncertainty based on the uncertainty of the container volume at two adjacent moments; and an eighth determination unit for determining a third leakage rate uncertainty based on the first leakage rate uncertainty and the uncertainty of the container volume at the previous moment of the two adjacent moments.

[0134] Among them, the first leakage rate uncertainty represents the overall uncertainty of the primary circuit of the pressurized water reactor nuclear power plant; the second leakage rate uncertainty represents the measurement uncertainty of the primary circuit of the pressurized water reactor nuclear power plant; and the third leakage rate uncertainty represents the prediction uncertainty of the primary circuit of the pressurized water reactor nuclear power plant.

[0135] Each module in the aforementioned pressurized water reactor nuclear power plant primary circuit leakage rate uncertainty monitoring device can be implemented in whole or in part through software, hardware, or a combination thereof. Each module can be embedded in or independent of a processor in a computer device in the form of hardware, or can be stored in the computer device's memory in the form of software, so that the processor can call and execute the corresponding operations of each module.

[0136] In an exemplary embodiment, a computer device is provided, which may be a terminal. Its internal structure may be as shown in FIG7 . The computer device includes a processor, memory, an input / output interface, a communication interface, a display unit, and an input device. The processor, memory, and input / output interface are connected via a system bus, and the communication interface, display unit, and input device are connected to the system bus via the input / output interface. The processor of the computer device provides computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of the operating system and computer program 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 via wired or wireless communication, which may be achieved via Wi-Fi, a mobile cellular network, NFC (near-field communication), or other technologies. When executed by the processor, the computer program 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 produce a visual image and may 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, and the input device of the computer device can be a touch layer covering the display screen, or a button, trackball or touchpad set on the computer device casing, or an external keyboard, touchpad or mouse.

[0137] Those skilled in the art will understand that the structure shown in FIG7 is merely a block diagram of a portion of the structure related to the solution of the present application, and does not constitute a limitation on the computer device to which the solution of the present application is applied. The specific computer device may include more or fewer components than shown in the figure, or combine certain components, or have a different arrangement of components.

[0138] In an exemplary embodiment, a computer device is provided, including a memory and a processor, wherein a computer program is stored in the memory, and when the processor executes the computer program, the following steps are implemented:

[0139] Obtain the uncertainty influencing parameters of the primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments;

[0140] determining, based on uncertainty influencing parameters at two adjacent moments, a leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at a later moment of the two adjacent moments; wherein the uncertainty influencing parameters include at least one of a volume uncertainty of a container and a capacity uncertainty of a container of the primary circuit of the pressurized water reactor nuclear power plant;

[0141] Among them, the uncertainty influencing parameters at each moment are obtained in the following way:

[0142] According to the liquid state data of the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameters at the corresponding moment are determined.

[0143] 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:

[0144] Obtain the uncertainty influencing parameters of the primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments;

[0145] determining, based on uncertainty influencing parameters at two adjacent moments, a leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at a later moment of the two adjacent moments; wherein the uncertainty influencing parameters include at least one of a volume uncertainty of a container and a capacity uncertainty of a container of the primary circuit of the pressurized water reactor nuclear power plant;

[0146] Among them, the uncertainty influencing parameters at each moment are obtained in the following way:

[0147] According to the liquid state data of the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameters at the corresponding moment are determined.

[0148] In one embodiment, a computer program product is provided, comprising a computer program, which, when executed by a processor, implements the following steps:

[0149] Obtain the uncertainty influencing parameters of the primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments;

[0150] determining, based on uncertainty influencing parameters at two adjacent moments, a leakage rate uncertainty of a primary circuit of a pressurized water reactor nuclear power plant at a later moment of the two adjacent moments; wherein the uncertainty influencing parameters include at least one of a volume uncertainty of a container and a capacity uncertainty of a container of the primary circuit of the pressurized water reactor nuclear power plant;

[0151] Among them, the uncertainty influencing parameters at each moment are obtained in the following way:

[0152] According to the liquid state data of the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameters at the corresponding moment are determined.

[0153] Those skilled in the art will appreciate that all or part of the processes in the above-mentioned embodiment methods can be implemented by instructing the relevant hardware through a computer program, and 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-mentioned methods. Among them, any reference to memory, database or other media used in the embodiments provided in this application may include at least one of non-volatile and volatile memory. Non-volatile memory may include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory may 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). The database involved in the various embodiments provided herein may include at least one of a relational database and a non-relational database. Non-relational databases may include, but are not limited to, distributed databases based on blockchains. The processor involved in the various embodiments provided herein may be, but are not limited to, a general-purpose processor, a central processing unit, a graphics processing unit, a digital signal processor, a programmable logic unit, a data processing logic unit based on quantum computing, and the like.

[0154] The technical features of the above embodiments can be combined arbitrarily. To make the description concise, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0155] The above-described embodiments merely represent several implementation methods of the present application. While the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the present application. It should be noted that a person of ordinary skill in the art may make various modifications and improvements without departing from the spirit of the present application, and these modifications and improvements fall within the scope of protection of the present application. Therefore, the scope of protection of the present application shall be determined by the appended claims.

Claims

1. A method for monitoring the uncertainty of leakage rate of a primary circuit of a pressurized water reactor nuclear power plant, characterized in that: The method comprises: Obtain the uncertainty influencing parameters of the primary circuit of a pressurized water reactor nuclear power plant at two adjacent moments; Determining the leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the later of the two adjacent moments based on the uncertainty influencing parameters at the two adjacent moments; wherein the uncertainty influencing parameters include at least one of the uncertainty of the volume of the container and the uncertainty of the capacity of the container of the primary circuit of the pressurized water reactor nuclear power plant; Among them, the uncertainty influencing parameters at each moment are obtained in the following way: According to the liquid state data corresponding to the target container in the primary circuit of the pressurized water reactor nuclear power plant at the corresponding moment, the uncertainty influencing parameter at the corresponding moment is determined.

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

3. The method according to claim 2, characterized in that Determining 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 primary circuit environmental data and a preset primary circuit environmental uncertainty at the time; Density data of the liquid in the target container at the moment is determined 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 environmental data includes pressure data and temperature data of the primary loop of the pressurized water reactor nuclear power plant. Correspondingly, the primary loop environmental uncertainty includes temperature uncertainty and pressure uncertainty. Determining 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 environmental data, and the primary loop environmental uncertainty includes: Correcting the pressure data at the time according to the pressure uncertainty to obtain corrected pressure data at the time; and Correcting the temperature data at the time according to the temperature uncertainty to obtain corrected temperature data at the time; Different density data corresponding to different primary circuit environmental data of the liquid in the target container at the moment are determined 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, characterized in that Determining the uncertainty influencing parameter of the target container at the moment according to the density data includes: Obtaining the primary circuit environmental uncertainty at the time; wherein the primary circuit environmental uncertainty includes the uncertainty of the liquid level of the control tank, the uncertainty of the liquid level of the pressure relief tank, the uncertainty of the liquid level of the injection tank, the uncertainty of the liquid level of the drain tank, the uncertainty of the liquid level of the pit buffer tank, and the uncertainty of the liquid level of the leakage measurement container; Determining a fluid volume uncertainty of a primary circuit of the pressurized water reactor nuclear power plant based on the density data, the temperature uncertainty, and the pressure uncertainty; Determining the uncertainty of the volume of the container of the primary circuit of the pressurized water reactor nuclear power plant at the moment according to the uncertainty of the fluid volume and the uncertainty of the liquid level of the control tank; According to the liquid level uncertainty of the injection tank, the liquid level uncertainty of the pressure relief tank, the liquid level uncertainty of the drain tank, the liquid level uncertainty of the pit buffer tank and the liquid level uncertainty of the leakage measurement container, the container volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the said moment is determined.

6. The method according to claim 5, characterized in that Determining the fluid volume uncertainty of the primary circuit of the pressurized water reactor nuclear power plant based on the density data, the temperature uncertainty, and the pressure uncertainty includes: Determining a first rate of change and a second rate of change of the primary circuit of the pressurized water reactor nuclear power plant at the moment according to the density data, the pressure uncertainty, and the temperature uncertainty; wherein the first rate of change represents a rate of change of the fluid density corresponding to the primary circuit of the pressurized water reactor nuclear power plant with temperature change; and the second rate of change represents a rate of change of the fluid density corresponding to the primary circuit of the pressurized water reactor nuclear power plant with pressure change; Determining a fluid mass uncertainty of a primary circuit 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; The uncertainty of the fluid volume of the primary circuit of the pressurized water reactor nuclear power plant at the moment is determined according to the fluid mass uncertainty and each density data.

7. The method according to claim 5, characterized in that Determining the uncertainty of the container volume of the primary circuit of the pressurized water reactor nuclear power plant at the moment according to the uncertainty of the fluid volume and the uncertainty of the liquid level of the control tank includes: Determine a first sum of the square of the uncertainty of the fluid volume and the square of the uncertainty of the liquid level of the control tank; The square root of the first sum is used as the uncertainty of the container volume of the primary loop of the pressurized water reactor nuclear power plant at the moment.

8. The method according to any one of claims 1 to 7, 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 represents the overall leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant; the second leakage rate uncertainty represents the measurement uncertainty of the primary circuit of the pressurized water reactor nuclear power plant; and the third leakage rate uncertainty represents the prediction uncertainty of the primary circuit of the pressurized water reactor nuclear power plant; and determining the leakage rate uncertainty of the primary circuit of the pressurized water reactor nuclear power plant at the later of the two adjacent moments according to the uncertainty influencing parameters at the two adjacent moments includes: determining the first leakage rate uncertainty according to the uncertainty of the container volume at the two adjacent moments and the time difference between the two adjacent moments; determining the second leakage rate uncertainty according to the container volume uncertainty at the two adjacent moments; The third leak rate uncertainty is determined according to the first leak rate uncertainty and the container volume uncertainty at the previous moment of the two adjacent moments.

9. The method according to claim 8, characterized in that Determining the first leakage rate uncertainty according to the container volume uncertainty at the two adjacent moments and the time difference between the two adjacent moments includes: Determine a second sum of the square of the uncertainty of the container volume at the earlier moment and the square of the uncertainty of the container volume at the later moment, between the two adjacent moments; The ratio of the second sum to the time difference between the two adjacent moments is used as the first leak rate uncertainty.

10. The method according to claim 8, characterized in that Determining the second leakage rate uncertainty based on the container volume uncertainty at the two adjacent moments includes: Determine the third sum of the square of the uncertainty of the container volume at the earlier moment and the square of the uncertainty of the container volume at the later moment, between the two adjacent moments; The square root of the third sum is taken as the second leakage rate uncertainty.

11. The method according to claim 8, characterized in that Determining the third leakage rate uncertainty according to the first leakage rate uncertainty and the container volume uncertainty at the previous moment of the two adjacent moments includes: The difference between the first leakage rate uncertainty and the container volume uncertainty at the previous moment of the two adjacent moments is used as the third leakage rate uncertainty.

12. A device for monitoring the uncertainty of leakage rate of a primary circuit of a pressurized water reactor nuclear power plant, characterized in that: The device comprises: The data acquisition module obtains the uncertainty influencing parameters of the primary circuit of the pressurized water reactor nuclear power plant at two adjacent moments; The uncertainty determination module determines the PWR according to the uncertainty influencing parameters at the two adjacent moments. The uncertainty of the leakage rate of the primary circuit of the nuclear power plant at the later time between the two adjacent time instants; wherein the uncertainty influencing parameter includes at least one of the uncertainty of the volume of the container and the uncertainty of the capacity of the container of the primary circuit of the pressurized water reactor nuclear power plant; Among them, the uncertainty influencing parameters at each moment are obtained in the following way: The influencing parameter determination module determines the uncertainty influencing parameter at a corresponding moment according to the liquid state data corresponding to the target container in the primary circuit of the pressurized water reactor nuclear power plant at a corresponding moment.

13. A computer device comprising a memory and a processor, wherein the memory stores a computer program, wherein: When the processor executes the computer program, the steps of the method according to any one of claims 1 to 11 are implemented.

14. A computer-readable storage medium having a computer program stored thereon, characterized in that: When the computer program is executed by a processor, the steps of the method according to any one of claims 1 to 11 are implemented.

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

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