Thermal performance evaluation method for heat exchangers in nuclear power plant, and electronic device and medium

Abstract

A thermal performance evaluation method for heat exchangers in a nuclear power plant, and an electronic device and a medium. The method comprises: first, acquiring the current heat exchange parameter of a heat exchanger in a nuclear power plant; extracting an environment-dependent parameter and an environment-independent parameter from the current heat exchange parameter; determining a thermal performance reference condition on the basis of the environment-dependent parameter and the environment-independent parameter; analyzing the current heat exchange parameter to obtain a current fouling thermal resistance corresponding to the heat exchanger in the nuclear power plant; and performing thermal performance evaluation on the current fouling thermal resistance on the basis of the thermal performance reference condition, so as to obtain thermal performance evaluation data. In this way, the thermal performance of heat exchangers in a nuclear power plant can be evaluated more accurately.

Description

Method for evaluating thermal performance of heat exchanger of nuclear power plant, electronic device and medium TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear power plants, in particular to a method for evaluating the thermal performance of a heat exchanger of a nuclear power plant, an electronic device and a medium. BACKGROUND

[0002] The device cooling water heat exchanger of a nuclear power plant bears important operation and safety functions. During normal operation or accidents of the nuclear power plant, it is used to remove heat from the device to meet the operating conditions of the user device and ensure the safety of the nuclear power plant. If the device cooling water heat exchanger fails, such as fouling or blockage, the operation and safety functions it bears cannot be realized, which will affect the economy and safety of the nuclear power plant. Therefore, it is necessary to evaluate the thermal performance of the operating device cooling water heat exchanger.

[0003] In related technologies, nuclear power plant maintenance personnel need to collect heat exchange parameters on the cold and hot sides of the heat exchanger, such as flow, inlet and outlet temperature, calculate the actual heat transfer coefficient, and compare the actual heat transfer coefficient with the heat transfer coefficient corresponding to the design accident condition, to evaluate the thermal performance of the heat exchanger. However, this method does not take into account the changes in operating conditions in actual operation, such as seasonal changes in seawater temperature and flow, and the occurrence of fouling or blockage, so it has certain limitations. SUMMARY

[0004] The present application aims to at least solve one of the technical problems existing in the prior art. To this end, the present application proposes a method for evaluating the thermal performance of a heat exchanger of a nuclear power plant, an electronic device and a medium, which can more accurately evaluate the thermal performance of the heat exchanger of the nuclear power plant.

[0005] The method for evaluating the thermal performance of a heat exchanger of a nuclear power plant according to the first aspect of the present application comprises:

[0006] obtaining current heat exchange parameters of a heat exchanger of a nuclear power plant;

[0007] extracting environment-related parameters and environment-independent parameters from the current heat exchange parameters; wherein the environment-related parameters are used to represent current heat exchange parameters associated with the environment of the heat exchanger of the nuclear power plant, and the environment-independent parameters are used to represent current heat exchange parameters independent of the environment of the heat exchanger of the nuclear power plant;

[0008] determining a thermal performance reference condition according to the environment-related parameters and the environment-independent parameters;

[0009] analyzing the current heat exchange parameters to obtain the current fouling thermal resistance corresponding to the heat exchanger of the nuclear power plant;

[0010] performing thermal performance evaluation on the current fouling resistance based on the thermal performance benchmark condition, to obtain thermal performance evaluation data.

[0011] According to some embodiments of the present application, the environment-related parameters include current cold-side flow rate and current cold-side inlet temperature, and the environment-independent parameters include working condition thermal-side flow rate and working condition thermal-side outlet temperature.

[0012] The determining of the thermal performance benchmark condition according to the environment-related parameters and the environment-independent parameters comprises:

[0013] determining heat exchange area, thermal-side specific heat capacity, cold-side specific heat capacity and working condition required heat quantity corresponding to the nuclear power plant heat exchanger;

[0014] performing benchmark calculation according to the heat exchange area, the thermal-side specific heat capacity, the cold-side specific heat capacity, the working condition required heat quantity, the current cold-side flow rate, the current cold-side inlet temperature, the working condition thermal-side flow rate and the working condition thermal-side outlet temperature, to obtain the thermal performance benchmark data;

[0015] determining the thermal performance benchmark condition according to the thermal performance benchmark data.

[0016] According to some embodiments of the present application, the performing of the benchmark calculation according to the heat exchange area, the thermal-side specific heat capacity, the cold-side specific heat capacity, the working condition required heat quantity, the current cold-side flow rate, the current cold-side inlet temperature, the working condition thermal-side flow rate and the working condition thermal-side outlet temperature, to obtain the thermal performance benchmark data, comprises:

[0017] generating a first analytical element according to the working condition thermal-side flow rate, the thermal-side specific heat capacity, the current cold-side flow rate and the cold-side specific heat capacity;

[0018] generating a second analytical element according to the working condition thermal-side outlet temperature and the current cold-side inlet temperature;

[0019] generating a third analytical element according to the working condition required heat quantity, the first analytical element and the second analytical element;

[0020] generating a fourth analytical element based on the product of the heat exchange area and the first analytical element;

[0021] generating the thermal performance benchmark data based on the third analytical element and the fourth analytical element.

[0022] According to some embodiments of the present application, the determining of the thermal performance benchmark condition according to the thermal performance benchmark data comprises:

[0023] determining a non-fouling theoretical thermal resistance corresponding to the nuclear power plant heat exchanger;

[0024] determining a thermal resistance reference threshold according to the thermal performance reference data and the non-fouling theoretical thermal resistance;

[0025] setting the thermal performance reference condition according to the thermal resistance reference threshold.

[0026] According to some embodiments of the present application, the determining a non-fouling theoretical thermal resistance corresponding to the nuclear power plant heat exchanger comprises:

[0027] obtaining heat exchanger design parameters and material characteristic information of the nuclear power plant heat exchanger;

[0028] calculating the non-fouling theoretical thermal resistance based on the heat exchanger design parameters and the material characteristic information.

[0029] According to some embodiments of the present application, the performing thermal performance evaluation on the current fouling thermal resistance based on the thermal performance reference condition to obtain thermal performance evaluation data comprises:

[0030] in response to the current fouling thermal resistance being greater than the thermal resistance reference threshold, determining that the current fouling thermal resistance meets the thermal performance reference condition, generating the performance qualified data, and determining the performance qualified data as the thermal performance evaluation data;

[0031] in response to the current fouling thermal resistance being less than or equal to the thermal resistance reference threshold, determining that the current fouling thermal resistance does not meet the thermal performance reference condition, generating the thermal performance failure data, and determining the performance failure data as the thermal performance evaluation data.

[0032] According to some embodiments of the present application, the determining a thermal performance reference condition according to the environment-related parameters and the environment-independent parameters comprises:

[0033] setting a corresponding environment-related margin for the environment-related parameters;

[0034] determining the thermal performance reference condition according to the environment-related parameters, the environment-related margin and the environment-independent parameters.

[0035] According to some embodiments of the present application, the performing analysis on the current heat exchange parameter to obtain a current fouling thermal resistance corresponding to the nuclear power plant heat exchanger comprises:

[0036] determining a non-fouling theoretical heat transfer coefficient corresponding to the nuclear power plant heat exchanger;

[0037] determining a current heat transfer coefficient based on the current heat exchange parameter;

[0038] According to the current heat transfer coefficient and the clean theory heat transfer coefficient, a current fouling thermal resistance corresponding to the heat exchanger of the nuclear power plant is calculated.

[0039] According to some embodiments of the present application, the calculation of the current fouling thermal resistance corresponding to the heat exchanger of the nuclear power plant according to the current heat transfer coefficient and the clean theory heat transfer coefficient comprises:

[0040] According to the current heat transfer coefficient, a first thermal resistance calculation element is constructed.

[0041] According to the clean theory heat transfer coefficient, a second thermal resistance calculation element is constructed.

[0042] The first thermal resistance calculation element and the second thermal resistance calculation element are combined to calculate the current fouling thermal resistance.

[0043] According to some embodiments of the present application, the construction of the first thermal resistance calculation element according to the current heat transfer coefficient comprises:

[0044] A first inverse proportionality parameter corresponding to the current heat transfer coefficient is determined as the first thermal resistance calculation element.

[0045] According to some embodiments of the present application, the construction of the second thermal resistance calculation element according to the clean theory heat transfer coefficient comprises:

[0046] A second inverse proportionality parameter corresponding to the clean theory heat transfer coefficient is determined as the second thermal resistance calculation element.

[0047] According to some embodiments of the present application, the combination of the first thermal resistance calculation element and the second thermal resistance calculation element to calculate the current fouling thermal resistance comprises:

[0048] The first thermal resistance calculation element and the second thermal resistance calculation element are calculated by difference processing to obtain the current fouling thermal resistance.

[0049] According to some embodiments of the present application, the heat exchanger of the nuclear power plant comprises heat transfer heat and heat exchange average temperature difference, and the determination of the current heat transfer coefficient based on the current heat exchange parameter comprises:

[0050] The effective heat exchange area of the heat exchanger of the nuclear power plant is determined.

[0051] Based on the heat transfer heat, the heat exchange average temperature difference and the effective heat exchange area, the current heat transfer coefficient is calculated in real time.

[0052] In a second aspect, an electronic device is provided, which comprises a memory and a processor. The memory stores a computer program. The processor executes the computer program to implement the method for evaluating thermal performance of a heat exchanger of a nuclear power plant according to any one of the embodiments of the first aspect of the present application.

[0053] In a third aspect, a computer readable storage medium is provided, which stores a program. The program is executed by a processor to implement the method for evaluating thermal performance of a heat exchanger of a nuclear power plant according to any one of the embodiments of the first aspect of the present application.

[0054] According to the method for evaluating thermal performance of a heat exchanger of a nuclear power plant, the electronic device and the medium provided by the embodiments of the present application have at least the following beneficial effects:

[0055] According to the method for evaluating thermal performance of a heat exchanger of a nuclear power plant, the electronic device and the medium provided by the embodiments of the present application have at least the following beneficial effects:

[0056] Additional aspects and advantages of the present application will be made apparent by the following description and the accompanying drawings. BRIEF DESCRIPTION OF DRAWINGS

[0057] The above and / or additional aspects and advantages of the present application will become apparent and be readily appreciated from the following description, including the accompanying drawings, wherein:

[0058] FIG. 1 is a flowchart of a method for evaluating thermal performance of a heat exchanger of a nuclear power plant according to an embodiment of the present application;

[0059] FIG. 2 is another flowchart of a method for evaluating thermal performance of a heat exchanger of a nuclear power plant according to an embodiment of the present application;

[0060] FIG. 3 is another flowchart of a method for evaluating thermal performance of a heat exchanger of a nuclear power plant according to an embodiment of the present application;

[0061] Fig. 4 is another flow diagram of the method for evaluating the thermal performance of the heat exchanger of the nuclear power plant according to an embodiment of the present application;

[0062] Fig. 5 is another flow diagram of the method for evaluating the thermal performance of the heat exchanger of the nuclear power plant according to an embodiment of the present application;

[0063] Fig. 6 is another flow diagram of the method for evaluating the thermal performance of the heat exchanger of the nuclear power plant according to an embodiment of the present application;

[0064] Fig. 7 is another flow diagram of the method for evaluating the thermal performance of the heat exchanger of the nuclear power plant according to an embodiment of the present application;

[0065] Fig. 8 is another flow diagram of the method for evaluating the thermal performance of the heat exchanger of the nuclear power plant according to an embodiment of the present application;

[0066] Fig. 9 is a schematic diagram of the hardware structure of an electronic device according to an embodiment of the present application. DETAILED DESCRIPTION

[0067] The embodiments of the present application are described in detail below with reference to the accompanying drawings. The embodiments described below are examples for explaining the present application and should not be understood as limiting the present application.

[0068] In the description of the present application, the singular form "a", "an" and "the" refer to the one or more, and the plural form "a plurality of" means two or more. Greater than, less than, more than, less than, etc. are understood as not including the number, and above, below, etc. are understood as including the number. If it is described as first, second, etc., it is only for the purpose of distinguishing technical features, and should not be understood as indicating or implying relative importance or implicitly indicating the number of indicated technical features or the order of indicated technical features.

[0069] In the description of the present application, it should be understood that the orientation description, such as up, down, left, right, front, back, etc. indicates the orientation or positional relationship based on the orientation or positional relationship shown in the drawings, which is only for the purpose of describing the present application and simplifying the description, and does not indicate or imply that the device or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore should not be understood as limiting the present application.

[0070] In the description of the specification, the description of the terms "one embodiment", "some embodiments", "exemplary embodiment", "example", "specific example", or "some examples" and the like means that the specific features, structures, materials or characteristics described in connection with the embodiment or example are included in at least one embodiment or example of the present application. In the specification, the exemplary description of the above terms does not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described can be combined in any one or more embodiments or examples in a suitable manner.

[0071] In the description of the present application, it should be noted that, unless otherwise explicitly limited, the words such as setting, installing, connecting and the like should be understood in a broad sense, and those skilled in the art can reasonably determine the specific meaning of the above words in the present application in combination with the specific content of the technical solution. In addition, the identification of the specific steps in the following does not represent the limitation of the order and execution logic of the steps, and the execution order and execution logic between the steps should be understood and inferred with reference to the content expressed in the embodiments.

[0072] The equipment cooling water heat exchanger of the nuclear power plant undertakes important operation and safety functions. During normal operation or accident of the nuclear power plant, it is used to lead out heat of the equipment to meet the operation conditions of the user equipment and ensure the safety of the nuclear power plant. It should be pointed out that as a passive device, the internal components of the heat exchanger will age, deform, corrode and scale, etc., which will cause equipment failure, resulting in unplanned shutdown of the heat exchange system, causing huge safety problems and economic losses.

[0073] The equipment cooling water heat exchanger of the nuclear power plant has many users on the hot side, and the operation of the users changes with the working condition of the nuclear power plant. Therefore, the flow and inlet temperature of the heat exchanger on the hot side change with the working condition of the nuclear power plant. At the same time, the flow of the equipment cooling water heat exchanger of the nuclear power plant on the cold side changes with the sea level, and the sea water temperature on the cold side of the heat exchanger also changes with the season.

[0074] If the equipment cooling water heat exchanger fails, such as fouling or blockage, its operation and safety functions cannot be realized, which will affect the economy and safety of the nuclear power plant. Therefore, it is necessary to evaluate the thermal performance of the running equipment cooling water heat exchanger.

[0075] In the related art, the operation and maintenance personnel of the nuclear power plant need to collect the heat exchange parameters of the cold and hot sides of the heat exchanger, such as flow, inlet and outlet temperature, calculate the actual heat transfer coefficient, and compare the actual heat transfer coefficient with the heat transfer coefficient corresponding to the design accident condition, so as to evaluate the thermal performance of the heat exchanger. However, this method does not take into account the changes in the actual operation, such as seasonal changes in sea water temperature and flow, and the occurrence of fouling or blockage, etc., so there is a certain limitation.

[0076] The present application aims to at least solve one of the technical problems existing in the prior art. To this end, the present application provides a thermal performance evaluation method for a nuclear power plant heat exchanger, an electronic device and a medium, which can more accurately evaluate the thermal performance of the nuclear power plant heat exchanger.

[0077] Further description will be made below with reference to the accompanying drawings.

[0078] Referring to FIG. 1, the thermal performance evaluation method for a nuclear power plant heat exchanger according to an embodiment of the present application comprises:

[0079] Step S101, obtaining the current heat exchange parameters of the nuclear power plant heat exchanger;

[0080] Step S102, extracting the environment-related parameters and the environment-independent parameters from the current heat exchange parameters; wherein the environment-related parameters are used to represent the current heat exchange parameters of the nuclear power plant heat exchanger associated with the environment, and the environment-independent parameters are used to represent the current heat exchange parameters of the nuclear power plant heat exchanger independent of the environment;

[0081] Step S103, determining the thermal performance benchmark condition according to the environment-related parameters and the environment-independent parameters;

[0082] Step S104, analyzing the current heat exchange parameters to obtain the current fouling resistance corresponding to the nuclear power plant heat exchanger;

[0083] Step S105, performing thermal performance evaluation on the current fouling resistance based on the thermal performance benchmark condition to obtain thermal performance evaluation data.

[0084] For the technical problems encountered in the actual operation of the nuclear power plant equipment cooling water heat exchanger, the thermal performance evaluation method proposed in the present application adopts a more detailed and dynamic evaluation strategy. First, the present embodiment obtains the current heat exchange parameters of the nuclear power plant heat exchanger, including flow rate, inlet and outlet temperature and other key parameters, which provides basic data for evaluation. Then, these parameters are further subdivided into environment-related parameters and environment-independent parameters. The environment-related parameters, such as seawater temperature and flow rate, are directly affected by seasonal changes, while the environment-independent parameters are not affected by these external environmental changes.

[0085] By this distinction, the performance of the heat exchanger under the current actual operating conditions can be more accurately reflected. Next, the embodiments of the present application determine the benchmark condition of the thermal performance using these parameters, which is equivalent to setting a reasonable expected value for the performance of the heat exchanger, which takes into account the influence of environmental factors. Subsequently, by analyzing the current heat exchange parameters, the embodiments of the present application can calculate the current fouling resistance of the heat exchanger, which is a key indicator for evaluating the performance of the heat exchanger, because it is directly related to the heat transfer efficiency of the heat exchanger.

[0086] Finally, based on the determined benchmark condition of the thermal performance, the current fouling resistance is evaluated for the thermal performance to obtain thermal performance evaluation data. This step is crucial because it not only provides a quantitative evaluation of the current performance of the heat exchanger, but also reveals whether the heat exchanger needs to be cleaned or repaired. Through this method, the performance state of the heat exchanger can be more accurately judged by the operators of the nuclear power plant, and timely measures can be taken to avoid the risk of operation and safety caused by fouling or blockage, etc., so as to ensure the economy and safety of the nuclear power plant. The implementation of this evaluation method makes the thermal performance evaluation of the heat exchanger more scientific and reasonable, and can adapt to the changing operating environment, improving the accuracy and practicality of the evaluation.

[0087] In step S101 of some embodiments, the current heat exchange parameters of the heat exchanger of the nuclear power plant are obtained.

[0088] It should be noted that in the process of thermal performance evaluation of the heat exchanger of the nuclear power plant, obtaining the current heat exchange parameters is crucial because it provides basic data for subsequent performance analysis. The current heat exchange parameters include a series of parameters directly related to the operating state of the heat exchanger, which can reflect the working condition of the heat exchanger at a specific time. In some embodiments, the current heat exchange parameters can specifically include the following types:

[0089] The inlet and outlet temperatures of the heat exchanger, including the inlet and outlet temperatures of the hot side and the cold side. These temperature data are key to calculating the heat transfer coefficient and the heat load, because they are directly related to the heat transfer efficiency of the heat exchanger. Temperature measurement is usually achieved by sensors installed at the inlet and outlet of the heat exchanger, which can provide real-time temperature readings.

[0090] The flow rate of the heat exchanger, the measurement of the flow rate is also an important part of obtaining the current heat exchange parameters. The flow rate reflects the speed of the fluid passing through the heat exchanger, which is also important for evaluating the thermal performance of the heat exchanger. The flow rate can be measured by various types of flow meters, such as electromagnetic flow meters, vortex flow meters, etc., which can provide accurate flow rate data.

[0091] In addition to temperature and flow rate, the current heat exchange parameters can also include other factors that may affect the performance of the heat exchanger, such as the pressure, chemical composition of the fluid, etc. Although these parameters are not direct heat exchange parameters, they may indirectly affect the operating state of the heat exchanger, and therefore need to be measured and recorded in some cases.

[0092] Step S102 of some embodiments extracts the environment-related parameters and the environment-independent parameters from the current heat exchange parameters; wherein the environment-related parameters are used to represent the current heat exchange parameters of the nuclear power plant heat exchanger associated with the environment, and the environment-independent parameters are used to represent the current heat exchange parameters of the nuclear power plant heat exchanger independent of the environment.

[0093] It should be noted that in the thermal performance evaluation of the heat exchanger of the nuclear power plant, the environment-related parameters and the environment-independent parameters are extracted from the current heat exchange parameters, the purpose of which is to distinguish different factors affecting the performance of the heat exchanger, so as to more accurately evaluate its performance and develop corresponding maintenance strategies.

[0094] The environment-related parameters refer to those parameters directly affected by external environmental conditions. In the heat exchanger of the nuclear power plant, such environment-related parameters can include the inlet temperature and flow rate of seawater. For example, the temperature of seawater changes with the seasons and weather, thereby affecting the heat transfer efficiency of the heat exchanger. Similarly, the flow rate of seawater may fluctuate due to changes in natural conditions such as tides, waves, etc., thereby affecting the cooling effect of the heat exchanger. Therefore, extracting these environment-related parameters separately helps to distinguish and quantify the specific impact of the current environmental conditions on the performance of the heat exchanger.

[0095] The environment-independent parameters refer to those parameters not directly affected by external environmental conditions. These environment-independent parameters more reflect the performance characteristics of the heat exchanger itself, such as the material properties, structural design, fouling resistance of the heat exchanger, etc. For example, the fouling resistance of the heat exchanger is caused by internal fouling accumulation, which has little to do with external environmental conditions, but has a significant impact on the heat transfer efficiency of the heat exchanger. By analyzing the environment-independent parameters, it can be determined whether the performance of the heat exchanger itself meets the design requirements and whether there is room for improvement.

[0096] Step S103 of some embodiments determines the thermal performance benchmark condition according to the environment-related parameters and the environment-independent parameters.

[0097] ​In the process of thermal performance evaluation of heat exchangers in nuclear power plants, determining the thermal performance benchmark condition involves considering both environment-dependent parameters and environment-independent parameters to establish a benchmark that reflects the performance of the heat exchanger under specific conditions. Environment-dependent parameters, such as seawater temperature and flow rate, are directly affected by external environmental conditions, while environment-independent parameters are more related to the design and state of the heat exchanger itself.

[0098] Firstly, environment-dependent parameters provide information about the operation of the heat exchanger under different environmental conditions. For example, seasonal changes in seawater temperature can affect the heat load and heat transfer efficiency of the heat exchanger. By analyzing these parameters, the expected performance of the heat exchanger under different environmental conditions can be determined. This helps to evaluate whether the heat exchanger can adapt to environmental changes and whether additional measures need to be taken to ensure its performance.

[0099] Secondly, environment-independent parameters provide important information about the performance of the heat exchanger itself. These parameters include the material, structure, and fouling resistance of the heat exchanger, which are not affected by external environmental conditions but have a direct impact on the thermal performance of the heat exchanger. By analyzing these parameters, it can be evaluated whether the design and maintenance of the heat exchanger meet the requirements for long-term operation.

[0100] In determining the thermal performance benchmark condition, both types of parameters need to be combined. For example, a comprehensive evaluation model can be established that takes into account the impact of environmental changes and the characteristics of the heat exchanger itself on performance. For another example, through historical data and simulation analysis, the optimal performance of the heat exchanger under specific environmental conditions can be determined. This optimal performance can be used as a benchmark for thermal performance to evaluate the performance of the heat exchanger in actual operation.

[0101] Referring to FIG. 2, according to some embodiments of the present application, the environment-dependent parameters include the current cold side flow rate and the current cold side inlet temperature, and the environment-independent parameters include the working condition hot side flow rate and the working condition hot side outlet temperature. Step S103 determines the thermal performance benchmark condition according to the environment-dependent parameters and the environment-independent parameters, including:

[0102] Step S201 determines the heat exchange area, the specific heat capacity of the hot side, the specific heat capacity of the cold side, and the working condition heat demand corresponding to the heat exchanger of the nuclear power plant;

[0103] Step S202 performs benchmark calculation according to the heat exchange area, the specific heat capacity of the hot side, the specific heat capacity of the cold side, the working condition heat demand, the current cold side flow rate, the current cold side inlet temperature, the working condition hot side flow rate, and the working condition hot side outlet temperature to obtain thermal performance benchmark data;

[0104] Step S203 determines the thermal performance benchmark condition according to the thermal performance benchmark data.

[0105] In some embodiments of the present application, the distinction between environment-dependent and environment-independent parameters is crucial when performing the thermal performance assessment of the heat exchanger in a nuclear power plant. Environment-dependent parameters, including the current cold-side flow rate and the current cold-side inlet temperature, are closely related to the environmental conditions in which the heat exchanger is located. For example, the cold-side inlet temperature can be influenced by the sea water temperature, while the cold-side flow rate can be related to the flow conditions of the sea water or the working state of the pump. Changes in these parameters directly reflect the influence of external environmental conditions on the performance of the heat exchanger. In contrast, environment-independent parameters, such as the hot-side flow rate and the hot-side outlet temperature, are more related to the internal operating state of the heat exchanger, and they are not directly affected by external environmental conditions. The hot-side flow rate and outlet temperature can provide important information about the internal heat transfer efficiency and heat load of the heat exchanger.

[0106] In step S201 of some embodiments, the first step is to determine the thermal performance baseline conditions. This includes determining the effective heat transfer area of the heat exchanger in the nuclear power plant, the specific heat capacity of the hot side, the specific heat capacity of the cold side, and the heat demand under the working condition. The heat transfer area is a key parameter in the design of the heat exchanger, which determines the maximum heat transfer potential of the heat exchanger. The specific heat capacities of the hot side and the cold side are physical properties of the fluids, which affect the efficiency of heat transfer. The heat demand under the working condition reflects the heat load demand of the heat exchanger in the nuclear power plant under a specific working condition.

[0107] In step S202 of some embodiments, baseline calculations are performed using these baseline conditions and the current heat exchange parameters. This calculation process involves complex thermodynamic and fluid mechanics models to ensure the accuracy of the assessment. By combining the heat transfer area, specific heat capacity, heat demand under the working condition, and actual flow rate and temperature data, thermal performance baseline data can be calculated. These data may include key parameters such as baseline heat transfer coefficient, baseline fouling resistance, etc., which are the basis for assessing the performance of the heat exchanger.

[0108] Referring to FIG. 3, according to some embodiments of the present application, step S202 performs baseline calculations based on the heat transfer area, the specific heat capacity of the hot side, the specific heat capacity of the cold side, the heat demand under the working condition, the current cold-side flow rate, the current cold-side inlet temperature, the working hot-side flow rate, and the working hot-side outlet temperature, to obtain thermal performance baseline data, including:

[0109] In step S301, a first analytical element is generated based on the working hot-side flow rate, the specific heat capacity of the hot side, the current cold-side flow rate, and the specific heat capacity of the cold side;

[0110] In step S302, a second analytical element is generated by subtracting the working hot-side outlet temperature from the current cold-side inlet temperature;

[0111] In step S303, a third analytical element is generated based on the heat demand under the working condition, the first analytical element, and the second analytical element;

[0112] Step S304: Generate the fourth analytical element based on the product of the heat exchange area and the first analytical element;

[0113] Step S305: Generate thermal performance benchmark data based on the third and fourth analytical elements.

[0114] In some embodiments, the heat exchange area is denoted as S, and the specific heat capacity on the hot side is denoted as CP. h The specific heat capacity of the cold side is expressed as CP. c The required heat under operating conditions is expressed as POW. IAC The current cold-side flow rate is expressed as Q. c The current cold-side inlet temperature is expressed as T. i c. The heat flow rate under operating conditions is expressed as Q. h_IAC The operating condition hot-side outlet temperature is expressed as T. o h IAC .

[0115] Based on this, step S301 calculates the heat-side flow rate Q under operating conditions. h_IAC Specific heat capacity of the hot side (CP) h Current cold-side flow rate Q c Cold side specific heat capacity CP c This generates the first parsed element. The first parsed element can be represented as:

[0116] It should be noted that the first analytical element integrates the heat capacity of the fluids on both sides of the heat exchanger, reflecting the fluid's ability to carry heat under certain flow rate and specific heat capacity conditions. The first analytical element is related to the heat transfer potential of the heat exchanger.

[0117] Furthermore, in step S302, based on the operating condition hot-side outlet temperature T... o h IAC With the current cold side inlet temperature T i The difference between c and the second parsed element can be represented as:

[0118] T o h IAC -T i c

[0119] It should be noted that the second analytical element is one of the key factors in measuring the efficiency of a heat exchanger, as it represents the temperature driving force achieved by the heat exchanger in actual operation. The larger this temperature difference, the higher the potential heat transfer capacity of the heat exchanger.

[0120] Furthermore, in step S303, the required heat output (POW) is determined based on the operating conditions. IAC First parsing element Second analytic element T o hIAC -T i c, the third analytical element, can be represented as:

[0121] It should be noted that the third analytical element combines the design requirements of the heat exchanger (such as the heat load under working conditions) with the actual operating conditions (such as the heat capacity of the fluid and the temperature difference) to assess whether the heat exchanger can meet the specific heat load requirements.

[0122] Further, step S304 generates a fourth analytical element based on the product of the heat exchange area S and the first analytical element , which can be represented as:

[0123] It should be noted that the heat exchange area, combined with the heat capacity of the fluid in the heat exchange process, forms the fourth analytical element, which can provide a more comprehensive perspective on the heat transfer potential of the heat exchanger.

[0124] Finally, the thermal performance benchmark data is generated based on the third analytical element and the fourth analytical element.

[0125] It should be noted that by combining the third analytical element as the denominator and the fourth analytical element as the numerator, the analytical expression of the maximum allowable thermal resistance Ra IAC of the heat exchanger as the thermal performance benchmark data can be obtained, which is represented as:

[0126] In step S203 of some embodiments, the benchmark conditions of the thermal performance are determined according to the data calculated by the benchmark. These benchmark conditions provide a scientific and reasonable reference standard for the performance evaluation of the heat exchanger. By comparing the actual operating data with these benchmark conditions, it can be accurately assessed whether the performance of the heat exchanger meets the design requirements and whether there is a risk of performance decline.

[0127] Referring to FIG. 4, according to some embodiments of the present application, step S203 determines the thermal performance benchmark conditions according to the thermal performance benchmark data, which includes:

[0128] Step S401 determines the non-fouling theoretical thermal resistance corresponding to the heat exchanger of the nuclear power plant;

[0129] Step S402 determines the thermal resistance benchmark threshold according to the thermal performance benchmark data and the non-fouling theoretical thermal resistance;

[0130] Step S403 sets the thermal performance benchmark conditions according to the thermal resistance benchmark threshold.

[0131] In step S401 of some embodiments, the non-fouling theoretical thermal resistance corresponding to the heat exchanger of the nuclear power plant is determined. The non-fouling theoretical thermal resistance is represented as It is important to note that the clean theoretical resistance refers to the resistance value of the heat exchanger under ideal conditions, i.e., without the influence of fouling or other deposits on the heat exchanger surface. This value is usually calculated based on the design parameters and material properties of the heat exchanger and represents the heat transfer efficiency of the heat exchanger in its best clean state.

[0132] According to some embodiments of the present application, determining the clean theoretical resistance corresponding to the heat exchanger of the nuclear power plant comprises:

[0133] Obtaining the heat exchanger design parameters and material property information of the heat exchanger of the nuclear power plant;

[0134] Based on the heat exchanger design parameters and material property information, the clean theoretical resistance is calculated.

[0135] In the performance evaluation process of the heat exchanger of the nuclear power plant, determining the clean theoretical resistance is a crucial step, as it provides a benchmark for the heat transfer efficiency of the heat exchanger under ideal conditions. This process involves two main steps: first, obtaining the design parameters and material property information of the heat exchanger of the nuclear power plant; second, calculating the clean theoretical resistance based on this information.

[0136] Obtaining the heat exchanger design parameters and material property information is the basis for determining the clean theoretical resistance. These information usually includes the type of heat exchanger (such as shell and tube, plate, etc.), size (such as pipe diameter, pipe length, pipe spacing, etc.), material (such as stainless steel, copper alloy, etc.) and specifications during manufacturing. These parameters are crucial for understanding the heat transfer performance of the heat exchanger, as they directly affect the heat transfer area, heat transfer coefficient and fluid dynamics characteristics of the heat exchanger.

[0137] Once the necessary design parameters and material property information are collected, the clean theoretical resistance can be calculated. This calculation is based on the basic theory of heat transfer, such as Fourier's law and Newton's cooling law, as well as the specific design of the heat exchanger.

[0138] In step S402 of some embodiments, the heat resistance benchmark threshold is determined according to the thermal performance benchmark data and the clean theoretical resistance. It is important to note that the heat resistance benchmark threshold is an important reference for evaluating whether the performance of the heat exchanger meets the standard, as it takes into account various conditions that the heat exchanger may encounter in actual operation, such as the temperature and flow of the fluid, the cleanliness of the heat exchanger, etc. By setting this threshold, it can ensure that the performance evaluation of the heat exchanger is both scientific and practical.

[0139] If the maximum heat resistance Ra IAC As the thermal performance benchmark data, the heat resistance benchmark threshold RE a , can be expressed as:

[0140] In step S403 of some embodiments, a thermal performance reference condition is set according to the thermal resistance reference threshold. It should be noted that the thermal resistance reference threshold is used as a key indicator to evaluate the performance of the heat exchanger, so as to determine whether the heat exchanger meets the operation requirements of the nuclear power plant. If the actual thermal resistance of the heat exchanger exceeds this threshold, it may mean that the heat exchanger needs to be cleaned or maintained to restore its heat transfer efficiency. On the contrary, if the thermal resistance is lower than the threshold, it indicates that the performance of the heat exchanger is good and can continue to operate normally.

[0141] Through the steps S201 to S203 shown in the embodiments of the present application, a comprehensive and accurate evaluation of the thermal performance of the heat exchanger of the nuclear power plant can be provided. This not only helps to ensure the efficient operation of the heat exchanger, but also helps to identify and solve possible performance problems in a timely manner, thereby ensuring the overall safety and reliability of the nuclear power plant.

[0142] Referring to FIG. 5, according to some embodiments of the present application, step S103 determines the thermal performance reference condition according to the environment-dependent parameter and the environment-independent parameter, including:

[0143] In step S501 of some embodiments, a corresponding environment-dependent margin is set for the environment-dependent parameter. The environment-dependent margin is a preventive measure that takes into account the possible fluctuations in external environmental conditions, such as seasonal changes in seawater temperature or fluctuations in flow rate. By setting the margin, it can be ensured that even if the environmental conditions deviate from the expected conditions, the heat exchanger can still meet its design requirements, thereby ensuring the stable operation of the nuclear power plant.

[0144] In step S502, the thermal performance reference condition is determined according to the environment-dependent parameter, the environment-dependent margin, and the environment-independent parameter.

[0145] In step S501 of some embodiments, a corresponding environment-dependent margin is set for the environment-dependent parameter. The environment-dependent margin is a preventive measure that takes into account the possible fluctuations in external environmental conditions, such as seasonal changes in seawater temperature or fluctuations in flow rate. By setting the margin, it can be ensured that even if the environmental conditions deviate from the expected conditions, the heat exchanger can still meet its design requirements, thereby ensuring the stable operation of the nuclear power plant.

[0146] In some embodiments, the setting of the environment-dependent margin can be based on historical data, environmental prediction models, or experience. For example, if historical data shows that seawater temperature may significantly increase in a particular season, a higher margin can be set for the cold side inlet temperature to ensure that the heat exchanger can still work effectively under high temperature conditions. Similarly, if the flow rate may decrease due to pump maintenance or failure, a margin can also be set for the cold side flow rate to cope with the situation of flow rate reduction.

[0147] In step S502 of some embodiments, the thermal performance reference condition is determined based on the environment-related parameters, the environment-related margins, and the environment-independent parameters. This step combines the actual values of the environment-related parameters, the margins set for these parameters, and the environment-independent parameters to determine the performance reference of the heat exchanger under the specific operating condition. This reference condition reflects the performance level that the heat exchanger should achieve after considering all relevant factors. For example, if the environment-related parameters show that the current cold-side inlet temperature is low, and the environment-independent parameters show that the hot-side flow rate is normal, the thermal performance reference condition can be adjusted to reflect the performance of the heat exchanger under this specific condition. In this way, the performance evaluation of the heat exchanger takes into account both the external environmental impact and the operating state of the heat exchanger itself.

[0148] Through the implementation of steps S501 to S502, the thermal performance reference condition is determined by setting the environment-related margins and combining the environment-independent parameters, providing a comprehensive performance evaluation framework for the heat exchanger. This method helps to identify and address various factors that may affect the performance of the heat exchanger, ensuring that the heat exchange system of the nuclear power plant can maintain efficient and reliable operation under various environmental conditions.

[0149] In some more specific embodiments, in the above process, the heat exchanger allowed maximum thermal resistance Ra IAC The analytical expression of the heat exchanger allowed maximum thermal resistance Ra IAC can be expressed as:

[0150] If a 4℃ margin is considered in the current cold-side inlet temperature represented as T i c IAC The analytical expression of the heat exchanger allowed maximum thermal resistance Ra IAC can be expressed as:

[0151] In this way, the thermal performance reference data can cope with fluctuations in seawater temperature within a certain range and have a certain degree of conservatism. The thermal performance reference data calculated according to the current weather conditions can reflect the real thermal performance requirements of the current heat exchanger, which can be used to guide the operation and maintenance work, reduce unnecessary maintenance operations, and thus more reasonably develop operation and maintenance strategies to improve production efficiency.

[0152] In step S104 of some embodiments, the current heat exchange parameters are analyzed to obtain the current fouling thermal resistance of the heat exchanger of the nuclear power plant.

[0153] In the thermal performance evaluation of the heat exchanger of the nuclear power plant, step S104 is to analyze the current heat exchange parameter to obtain the current fouling resistance of the heat exchanger. The fouling resistance refers to the additional resistance caused by the fouling layer accumulated on the heat transfer surface of the heat exchanger to the heat transfer, which is one of the important factors affecting the efficiency and performance of the heat exchanger.

[0154] Referring to FIG. 6, according to some embodiments of the present application, step S104 analyzes the current heat exchange parameter to obtain the current fouling resistance of the heat exchanger of the nuclear power plant, comprising:

[0155] Step S601, determining the clean theoretical heat transfer coefficient corresponding to the heat exchanger of the nuclear power plant;

[0156] Step S602, determining the current heat transfer coefficient based on the current heat exchange parameter;

[0157] Step S603, calculating the current fouling resistance of the heat exchanger of the nuclear power plant according to the current heat transfer coefficient and the clean theoretical heat transfer coefficient.

[0158] Step S601 of some embodiments needs to determine the clean theoretical heat transfer coefficient corresponding to the heat exchanger of the nuclear power plant. The clean theoretical heat transfer coefficient refers to the theoretical heat transfer coefficient of the heat exchanger under the assumption that the surface of the heat exchanger is completely clean and has no fouling effect. This value can be calculated according to the design parameters and material properties of the heat exchanger, providing a benchmark for performance comparison.

[0159] Step S602 of some embodiments determines the current heat transfer coefficient based on the current heat exchange parameter, such as the flow rate of the fluid, the inlet and outlet temperature, etc. The heat transfer coefficient is a key parameter for measuring the heat transfer efficiency of the heat exchanger, which can be calculated from the actual measured performance data of the heat exchanger. This coefficient reflects the actual heat transfer capacity of the heat exchanger under the current operating conditions.

[0160] Referring to FIG. 7, according to some embodiments of the present application, the heat exchanger of the nuclear power plant includes heat transfer heat and heat transfer average temperature difference, and step S602 determines the current heat transfer coefficient based on the current heat exchange parameter, comprising:

[0161] Step S701, determining the effective heat transfer area of the heat exchanger of the nuclear power plant;

[0162] Step S702, performing real-time calculation of the heat transfer coefficient based on the heat transfer heat, the heat transfer average temperature difference and the effective heat transfer area to obtain the current heat transfer coefficient.

[0163] In some embodiments, to obtain the current fouling resistance, first, the current heat exchange parameters need to be collected and analyzed, which can include the inlet and outlet temperatures of the heat exchanger, the flow rate of the fluid, the specific heat capacity of the fluid, etc. These current heat exchange parameters can be obtained by real-time monitoring through sensors installed on the heat exchanger. Then, the current heat transfer coefficient of the heat exchanger is calculated using these current heat exchange parameters. Specifically, the current heat transfer coefficient is a key parameter that measures the heat transfer efficiency of the heat exchanger, which can be calculated by the following formula:

[0164] where U is the heat transfer coefficient, Q is the heat transferred through the heat exchanger, A is the effective heat transfer area of the heat exchanger, and ΔT lm is the logarithmic mean temperature difference.

[0165] It should be noted that the heat exchange area S and the effective heat exchange area A are related but not necessarily identical concepts.

[0166] The heat exchange area S refers to the total heat exchange area of the heat exchanger, including all surfaces designed to transfer heat. This includes the surface area inside the pipes, the surface area outside the pipes, or the plate area in plate heat exchangers. In an ideal case, this area is calculated by the manufacturer based on the design parameters of the heat exchanger, which represents the maximum possible heat transfer capacity of the heat exchanger.

[0167] The effective heat exchange area A refers to the area that actually participates in heat exchange. In some cases, due to fouling, corrosion, scaling, or other operating conditions, a portion of the heat exchanger area may not be able to effectively transfer heat. Therefore, the effective heat exchange area refers to the portion of the area that can effectively exchange heat under actual operating conditions.

[0168] In an ideal state, if the heat exchanger is brand new and has no fouling or obstacles, the heat exchange area S and the effective heat exchange area A are equal. However, in actual applications, due to fouling and other factors, the effective heat exchange area A may be smaller than the total heat exchange area S.

[0169] In step S603 of some embodiments, the current fouling resistance corresponding to the heat exchanger of the nuclear power plant is calculated based on the current heat transfer coefficient and the theoretical fouling resistance. This calculation process can include comparing the actual observed heat transfer coefficient with the theoretical heat transfer coefficient in the absence of fouling, and through this comparison, the actual impact of fouling on the heat transfer efficiency of the heat exchanger can be evaluated. The calculated current fouling resistance provides a quantitative indicator for evaluating the cleanliness and performance degradation of the heat exchanger.

[0170] Next, the theoretical heat transfer coefficient of the heat exchanger in the clean state needs to be determined. The theoretical heat transfer coefficient can be determined based on the design parameters of the heat exchanger and the performance data in the clean state. With the theoretical heat transfer coefficient and the current heat transfer coefficient, the current fouling resistance can be calculated.

[0171] Specifically, the current fouling resistance can be estimated by the following formula:

[0172] wherein R f represents the current fouling resistance, U theoretical is the clean theoretical heat transfer coefficient in the clean state, and U actual is the current heat transfer coefficient.

[0173] According to some embodiments of the present application, the current fouling resistance of the heat exchanger of the nuclear power plant is calculated according to the current heat transfer coefficient and the clean theoretical heat transfer coefficient, comprising:

[0174] According to the current heat transfer coefficient, a first heat resistance calculation element is constructed;

[0175] According to the clean theoretical heat transfer coefficient, a second heat resistance calculation element is constructed;

[0176] The first heat resistance calculation element and the second heat resistance calculation element are combined to calculate the current fouling resistance.

[0177] According to some embodiments of the present application, the first heat resistance calculation element is constructed according to the current heat transfer coefficient, comprising:

[0178] The first inverse proportional quantity corresponding to the current heat transfer coefficient, i.e. is determined as the first heat resistance calculation element.

[0179] According to some embodiments of the present application, the second heat resistance calculation element is constructed according to the clean theoretical heat transfer coefficient, comprising:

[0180] The second inverse proportional quantity corresponding to the clean theoretical heat transfer coefficient, i.e. is determined as the second heat resistance calculation element.

[0181] According to some embodiments of the present application, the first heat resistance calculation element and the second heat resistance calculation element are combined to calculate the current fouling resistance, comprising:

[0182] The first heat resistance calculation element and the second heat resistance calculation element are calculated by difference, i.e. the current fouling resistance R f is obtained.

[0183] Some more specific embodiments can also take into account other factors during the calculation process, such as changes in the physical properties of the fluid, aging and corrosion of the heat exchanger, etc. These factors can all affect the performance of the heat exchanger and the accuracy of the fouling resistance assessment.

[0184] It should be understood that through the above analysis and calculation, the current fouling resistance of the heat exchanger in the nuclear power plant can be obtained. This value is an important basis for evaluating the performance of the heat exchanger and formulating maintenance strategies. For example, if the fouling resistance exceeds a preset threshold, it may mean that the heat exchanger needs to be cleaned or repaired to restore its heat transfer efficiency and ensure the safe and economic operation of the nuclear power plant. By conducting such analysis regularly, problems with the heat exchanger can be discovered and addressed in a timely manner, avoiding performance degradation and potential safety risks due to fouling accumulation.

[0185] Through the steps S601 to S603 shown in the embodiments of the present application, the performance status of the heat exchanger under the current operating conditions can be accurately evaluated, and the influence of fouling on the performance of the heat exchanger can be determined.

[0186] In step S105 of some embodiments, the thermal performance of the current fouling resistance is evaluated based on the thermal performance reference conditions, obtaining thermal performance evaluation data.

[0187] In the process of thermal performance evaluation of the heat exchanger in the nuclear power plant, step S105 needs to evaluate the current fouling resistance based on the thermal performance reference conditions, which is a key link to ensure the continuous and efficient operation of the heat exchanger. The thermal performance reference conditions refer to the performance indicators that the heat exchanger should have under ideal or standard conditions, which can be derived from design parameters, historical best performance data or manufacturer's specifications.

[0188] First of all, the reference conditions of thermal performance need to be established, which includes environmental related parameters such as sea water temperature, flow rate, etc. under certain environmental conditions, as well as environmental independent parameters such as heat transfer area, material properties, etc. of the heat exchanger itself. These thermal performance reference conditions provide a reference standard for the performance of the heat exchanger, making the performance evaluation comparable.

[0189] Next, the current fouling resistance calculated in step S104 is compared with the expected fouling resistance under the reference conditions to evaluate whether the performance of the heat exchanger meets the requirements. For example, if the current fouling resistance is significantly higher than the reference value, it means that the heat transfer efficiency of the heat exchanger has been seriously affected and cleaning or maintenance measures need to be taken. On the contrary, if the fouling resistance is close to or lower than the reference value, it indicates that the performance of the heat exchanger is within an acceptable range.

[0190] In the thermal performance evaluation, other factors that may affect the performance can also be considered, such as changes in the physical properties of the fluid, aging and corrosion of the heat exchanger, etc. These factors may work together with the fouling resistance to affect the overall performance of the heat exchanger. Therefore, these factors should be considered comprehensively in the evaluation process to obtain more comprehensive thermal performance evaluation data.

[0191] It should be understood that through the thermal performance evaluation, the corresponding thermal performance evaluation data of the heat exchanger can be obtained, which can not only include the comparison results of the current fouling resistance with the baseline condition, but also include key performance indicators such as heat transfer efficiency and heat load capacity of the heat exchanger. It should be noted that the thermal performance evaluation data are crucial for the operation and maintenance management of the nuclear power plant, which can help make decisions on whether to clean, repair or replace the heat exchanger in the operation and maintenance work of the heat exchanger, so as to ensure that the heat exchanger of the nuclear power plant is always in a good operating state, and to ensure the safe, stable and economic operation of the nuclear power plant. By regularly performing such thermal performance evaluation, the service life of the heat exchanger can be effectively prolonged, the risk of unexpected shutdown can be reduced, and the overall operation efficiency of the nuclear power plant can be improved.

[0192] Referring to FIG. 8, according to some embodiments of the present application, step S105 performs thermal performance evaluation on the current fouling resistance based on the thermal performance baseline condition to obtain thermal performance evaluation data, including:

[0193] Step S801, in response to the current fouling resistance being greater than the resistance baseline threshold, determines that the current fouling resistance meets the thermal performance baseline condition, generates performance qualified data, and determines the performance qualified data as the thermal performance evaluation data;

[0194] Step S802, in response to the current fouling resistance being less than or equal to the resistance baseline threshold, determines that the current fouling resistance does not meet the thermal performance baseline condition, generates thermal performance failure data, and determines the performance failure data as the thermal performance evaluation data.

[0195] In some embodiments of the present application, step S105 is a decisive link in the thermal performance evaluation process, which evaluates the current fouling resistance based on the thermal performance baseline condition and generates thermal performance evaluation data accordingly. This step is the key to ensure that the heat exchanger of the nuclear power plant continuously meets the performance requirements.

[0196] If the current fouling resistance is greater than the set resistance reference threshold in step S801 of some embodiments, it means that the fouling resistance of the heat exchanger is within an acceptable range, and the performance of the heat exchanger meets the thermal performance reference condition. In this case, the system generates performance qualified data indicating that the current working state of the heat exchanger is normal and there is no immediate cleaning or maintenance requirement. The performance qualified data is then determined as the thermal performance evaluation data, providing confirmation of good performance of the heat exchanger for the operation and maintenance tasks of the heat exchanger, so that they can continue to monitor the operation of the heat exchanger without the need to take additional measures.

[0197] If the current fouling resistance is less than or equal to the resistance reference threshold in step S802 of some embodiments, it indicates that the fouling resistance of the heat exchanger exceeds the acceptable range and does not meet the thermal performance reference condition. In this case, the system generates thermal performance failure data indicating that the heat exchanger may need to be cleaned or maintained to restore its heat transfer efficiency and prevent further performance degradation. The performance failure data is determined as the thermal performance evaluation data, providing a clear indication to the operation and maintenance tasks of the heat exchanger that further inspection and necessary maintenance work of the heat exchanger are required.

[0198] It should be understood that through this evaluation method based on the resistance reference threshold, the operating state of the heat exchanger can be effectively monitored and controlled. It not only helps to identify performance problems in a timely manner and avoid potential operational risks, but also optimizes maintenance plans and reduces unnecessary cleaning or maintenance work, thereby improving the operating efficiency and economy of the nuclear power plant.

[0199] Referring to FIG. 9, FIG. 9 illustrates a hardware structure of an electronic device according to another embodiment, which includes:

[0200] The processor 901 can be implemented in the form of a general-purpose CPU (Central Processing Unit), a microprocessor, an ASIC (Application Specific Integrated Circuit), or one or more integrated circuits, and is used to execute related programs to implement the technical solutions provided by the embodiments of the present application;

[0201] The memory 902 can be implemented in the form of Read-Only Memory (ROM), static storage device, dynamic storage device or Random Access Memory (RAM), etc. The memory 902 can store an operating system and other application programs, and when the technical solutions provided by the embodiments of the present specification are implemented by software or firmware, the related program codes are stored in the memory 902 and are called and executed by the processor 901 to perform the method for evaluating the thermal performance of the heat exchanger of the nuclear power plant according to the embodiments of the present application;

[0202] The input / output interface 903 is configured to realize information input and output.

[0203] The communication interface 904 is configured to realize the communication interaction between the device and other devices, and the communication can be realized in a wired manner (for example, USB, network cable, etc.) or in a wireless manner (for example, mobile network, WIFI, Bluetooth, etc.).

[0204] The bus 905 is configured to transmit information between various components (for example, the processor 901, the memory 902, the input / output interface 903 and the communication interface 904) of the device.

[0205] The processor 901, the memory 902, the input / output interface 903 and the communication interface 904 are connected to each other through the bus 905 to realize the communication connection between the device.

[0206] The embodiments of the present application also provide a computer program product, which includes a computer program. The processor of the computer device reads the computer program and executes, so that the computer device executes the method for evaluating the thermal performance of the heat exchanger of the nuclear power plant.

[0207] The terms "first", "second", "third", "fourth" and the like (if any) in the specification of the present application and the above-described drawings are used to distinguish similar objects, and do not necessarily indicate a specific order or sequence. It should be understood that the data thus used can be interchanged under appropriate circumstances, so that the embodiments of the present application described herein can be implemented in an order other than that illustrated or described herein. In addition, the terms "include" and "contain" and any variations thereof are intended to cover non-exclusive inclusion, for example, a process, method, system, product or device including a series of steps or units does not necessarily limit to the clearly listed steps or units, but can include other steps or units that are not clearly listed or inherent to the process, method, product or device.

[0208] It should be understood that, in the present application, "at least one" means one or more, and "multiple" means two or more. "And / or" is used to describe the relationship between associated objects, which means that there can be three relationships, for example, "A and / or B" can mean that there are three cases of A only, B only, and A and B at the same time, where A and B can be singular or plural. The character " / " generally represents an "or" relationship between the associated objects. "At least one of the following" or similar expressions means any combination of these items, including any combination of single or multiple items. For example, at least one of a, b or c can mean a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, and c can be single or multiple.

[0209] It should be understood that in the description of the embodiments of the present application, the meaning of multiple (or multiple) is two or more, greater than, less than, more than, etc. is not included in the number, and above, below, etc. is included in the number.

[0210] In several embodiments provided by the present application, it should be understood that the disclosed system, device and method can be implemented in other ways. For example, the device embodiments described above are only schematic, for example, the division of units is only a logical function division, and actual implementation can have another division manner, for example, multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. In addition, the coupling or direct coupling or communication connection between the displayed or discussed mutual ones can be indirect coupling or communication connection through some interfaces, devices or units, which can be electrical, mechanical or other forms.

[0211] The units described as separate components can or can not be physically separated, and the components shown as units can or can not be physical units, that is, they can be located in one place, or they can be distributed on multiple network units. Part or all of the units can be selected according to actual needs to achieve the purpose of the present embodiment.

[0212] In addition, the functional units in each embodiment of the present application can be integrated in one processing unit, or each unit can be physically present separately, or two or more units can be integrated in one unit. The above integrated unit can be realized in the form of hardware or in the form of software functional unit.

[0213] The integrated unit, if implemented in the form of a software function unit and sold or used as an independent product, can be stored in a computer readable storage medium. Based on such understanding, the technical solutions of the present application essentially or say the part that contributes to the prior art or the whole or part of the technical solutions can be embodied in the form of a software product. The computer software product is stored in a storage medium and includes a plurality of instructions for causing a computer device (which can be a personal computer, a server, or a network device, etc.) to execute all or part of the steps of the embodiments of the present application. The aforementioned storage medium includes: a U disk, a mobile hard disk, a read-only memory (ROM), a random access memory (RAM), a magnetic disk or an optical disk, and various media that can store program codes.

[0214] It should also be appreciated that the various embodiments provided by the present application can be combined arbitrarily to achieve different technical effects.

[0215] The above is a specific description of the embodiments of the present application, but the present application is not limited to the above embodiments. Those skilled in the art can make various equivalent modifications or replacements without departing from the spirit of the present application, and these equivalent modifications or replacements are included in the scope defined by the claims of the present application.

Claims

1. A method of evaluating thermal performance of a heat exchanger of a nuclear power plant, characterized by, The method comprises: acquiring a current heat exchange parameter of a nuclear power plant heat exchanger; extracting an environment-related parameter and an environment-unrelated parameter from the current heat exchange parameter, wherein the environment-related parameter is used to represent a current heat exchange parameter of the nuclear power plant heat exchanger related to an environment, and the environment-unrelated parameter is used to represent a current heat exchange parameter of the nuclear power plant heat exchanger unrelated to the environment; determining a thermal performance benchmark condition according to the environment-related parameter and the environment-unrelated parameter; analyzing the current heat exchange parameter to obtain a current fouling thermal resistance corresponding to the nuclear power plant heat exchanger; performing thermal performance evaluation on the current fouling thermal resistance based on the thermal performance benchmark condition to obtain thermal performance evaluation data.

2. The method of claim 1, wherein, The environment-related parameter comprises a current cold side flow rate and a current cold side inlet temperature, and the environment-unrelated parameter comprises a working condition hot side flow rate and a working condition hot side outlet temperature. The determining of the thermal performance benchmark condition according to the environment-related parameter and the environment-unrelated parameter comprises: determining a heat exchange area, a hot side specific heat capacity, a cold side specific heat capacity and a working condition required heat quantity corresponding to the nuclear power plant heat exchanger; performing benchmark calculation according to the heat exchange area, the hot side specific heat capacity, the cold side specific heat capacity, the working condition required heat quantity, the current cold side flow rate, the current cold side inlet temperature, the working condition hot side flow rate and the working condition hot side outlet temperature to obtain thermal performance benchmark data; determining the thermal performance benchmark condition according to the thermal performance benchmark data.

3. The method of claim 2, wherein, The performing of the benchmark calculation according to the heat exchange area, the hot side specific heat capacity, the cold side specific heat capacity, the working condition required heat quantity, the current cold side flow rate, the current cold side inlet temperature, the working condition hot side flow rate and the working condition hot side outlet temperature to obtain the thermal performance benchmark data comprises: generating a first analysis element according to the working condition hot side flow rate, the hot side specific heat capacity, the current cold side flow rate and the cold side specific heat capacity; generating a second analysis element by subtracting the working condition hot side outlet temperature from the current cold side inlet temperature; generating a third analysis element according to the working condition required heat quantity, the first analysis element and the second analysis element; generating a fourth analysis element based on a product of the heat exchange area and the first analysis element; generating the thermal performance benchmark data based on the third analysis element and the fourth analysis element.

4. The method of claim 2, wherein, The determining of the thermal performance benchmark condition according to the thermal performance benchmark data comprises: determining a clean theory thermal resistance corresponding to the nuclear power plant heat exchanger; determining a thermal resistance benchmark threshold according to the thermal performance benchmark data and the clean theory thermal resistance; setting the thermal performance benchmark condition according to the thermal resistance benchmark threshold.

5. The method of claim 4, wherein, The determining of the clean theory thermal resistance corresponding to the nuclear power plant heat exchanger comprises: acquiring exchanger design parameters and material characteristic information of the nuclear power plant heat exchanger; calculating the clean theory thermal resistance based on the exchanger design parameters and the material characteristic information.

6. The method of claim 4, wherein, The thermal performance evaluation data is obtained by performing thermal performance evaluation on the current fouling thermal resistance based on the thermal performance benchmark condition, and the thermal performance evaluation data comprises: In response to the current fouling thermal resistance being greater than the thermal resistance benchmark threshold, it is determined that the current fouling thermal resistance meets the thermal performance benchmark condition, the performance qualified data is generated, and the performance qualified data is determined as the thermal performance evaluation data; In response to the current fouling thermal resistance being less than or equal to the thermal resistance benchmark threshold, it is determined that the current fouling thermal resistance does not meet the thermal performance benchmark condition, the thermal performance failure data is generated, and the performance failure data is determined as the thermal performance evaluation data.

7. The method of claim 1, wherein, The thermal performance benchmark condition is determined according to the environment-related parameter and the environment-independent parameter, and the method comprises: An environment-related margin corresponding to the environment-related parameter is set; The thermal performance benchmark condition is determined according to the environment-related parameter, the environment-related margin and the environment-independent parameter.

8. The method of claim 1, wherein, The current fouling thermal resistance corresponding to the nuclear power plant heat exchanger is obtained by analyzing the current heat exchange parameter, and the method comprises: A non-fouling theoretical thermal resistance corresponding to the nuclear power plant heat exchanger is determined; A current heat transfer coefficient is determined based on the current heat exchange parameter; The current fouling thermal resistance corresponding to the nuclear power plant heat exchanger is obtained by calculation according to the current heat transfer coefficient and the non-fouling theoretical thermal resistance.

9. The method of claim 8, wherein, The current fouling thermal resistance corresponding to the nuclear power plant heat exchanger is obtained by calculation according to the current heat transfer coefficient and the non-fouling theoretical heat transfer coefficient, and the method comprises: A first thermal resistance calculation element is constructed according to the current heat transfer coefficient; A second thermal resistance calculation element is constructed according to the non-fouling theoretical heat transfer coefficient; The current fouling thermal resistance is obtained by calculation of the first thermal resistance calculation element and the second thermal resistance calculation element.

10. The method of claim 9, wherein, The first thermal resistance calculation element is constructed according to the current heat transfer coefficient, and the method comprises: A first inverse proportion parameter corresponding to the current heat transfer coefficient is determined as the first thermal resistance calculation element.

11. The method of claim 10, wherein, The second thermal resistance calculation element is constructed according to the non-fouling theoretical heat transfer coefficient, and the method comprises: A second inverse proportion parameter corresponding to the non-fouling theoretical heat transfer coefficient is determined as the second thermal resistance calculation element.

12. The method of claim 11, wherein, The current fouling thermal resistance is obtained by calculation of the first thermal resistance calculation element and the second thermal resistance calculation element, and the method comprises: The first thermal resistance calculation element and the second thermal resistance calculation element are calculated by difference processing to obtain the current fouling thermal resistance.

13. The method of claim 8, wherein, The nuclear power plant heat exchanger comprises heat transfer heat and heat exchange average temperature difference, and the current heat transfer coefficient is determined based on the current heat exchange parameter, and the method comprises: An effective heat exchange area of the nuclear power plant heat exchanger is determined; The current heat transfer coefficient is obtained by heat transfer coefficient real-time calculation based on the heat transfer heat, the heat exchange average temperature difference and the effective heat exchange area.

14. An electronic device, comprising: The method comprises: A memory and a processor, the memory stores a computer program, and the processor implements the nuclear power plant heat exchanger thermal performance evaluation method according to any one of claims 1 to 13 when executing the computer program.

15. A computer-readable storage medium, characterized in that, The storage medium stores a program, and the program is executed by the processor to implement the method for evaluating the thermal performance of the heat exchanger of the nuclear power plant according to any one of claims 1 to 13.

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