Method, device and equipment for determining accident information of nuclear power station and computer program
Through electronic equipment, the steam generator pressure and reactor temperature of the nuclear power plant are automatically obtained and processed, and the area where the state point is determined on the chart is determined, which solves the problem of low efficiency in determining accident information in the prior art and achieves more efficient automated processing.
Patent Information
- Application Number
- CN202411912216.5
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2024-12-20
- Publication Date
- 2025-04-11
AI Technical Summary
The existing nuclear power plant accident information is inefficient, mainly due to the need to manually read the current pressure of the steam generator and the current temperature of the reactor, and then view the area of the state point on the preset chart, resulting in inefficiency.
The current pressure of the steam generator and the current temperature of the reactor are automatically obtained by the electronic device, a first temperature threshold is determined based on the current pressure, and then the region where the state point corresponding to the current pressure and the current temperature is located in the preset chart is determined based on the current temperature and the first temperature threshold.
It improves the efficiency of determining nuclear power plant accident information, allowing electronic equipment to automatically complete the area determination of state points, which is faster and more accurate than manual methods.
Smart Images
Figure CN119811725A_ABST
Abstract
Description
Technical Field
[0001] The present application belongs to the technical field of nuclear power plants, and in particular, relates to a method, device, equipment and computer program for determining accident information of a nuclear power plant. Background Art
[0002] The steam generator heat transfer tube rupture accident in a nuclear power plant is a common design basis accident of a nuclear power plant. It is an accident caused by the rupture of several heat transfer tubes of the steam generator. When the heat transfer tube of the steam generator ruptures, the coolant in the primary circuit will leak into the steam generator, causing the radioactivity level of the secondary circuit to increase and the pressure of the primary circuit to decrease. When the pressure of the primary circuit drops to the pressure threshold, it will trigger protection actions such as reactor tripping and injection system startup.
[0003] When the injection system is started, it is necessary to determine whether it needs to be shut down based on the information of the nuclear power plant. The area on the preset chart where the state point corresponding to the current pressure of the steam generator and the current temperature of the reactor is located is the key information for determining whether the injection system needs to be shut down.
[0004] At present, the current pressure of the steam generator and the current temperature of the reactor are usually read manually, and then the state point corresponding to the current pressure of the steam generator and the current temperature of the reactor is checked on the preset chart to see the area on the preset chart, which reduces the efficiency of determining the accident information of the nuclear power plant. Summary of the invention
[0005] In view of this, the embodiments of the present application provide a method, device, electronic device and computer program for determining nuclear power plant accident information to solve the technical problem of low efficiency in determining existing nuclear power plant accident information.
[0006] In a first aspect, an embodiment of the present application provides a method for determining nuclear power plant accident information, comprising:
[0007] After determining that a heat transfer tube of a steam generator of a nuclear power plant is ruptured, obtaining a current pressure of the steam generator and a current temperature of a reactor of the nuclear power plant;
[0008] Determining a first temperature threshold according to the current pressure;
[0009] According to the current temperature and the first temperature threshold, determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located; wherein the preset chart includes a curve for describing the relationship between the pressure of the steam generator and the first temperature threshold.
[0010] Optionally, determining a first temperature threshold according to the current pressure includes:
[0011] Determine the saturation temperature according to the current pressure and a preset relationship; wherein the preset relationship is used to describe the relationship between the current pressure and the saturation temperature;
[0012] The first temperature threshold is determined according to the saturation temperature.
[0013] Optionally, the preset relationship is determined in the following manner:
[0014] Determining the saturation temperature corresponding to each of a plurality of preset pressures;
[0015] The preset relationship is determined according to the saturation temperatures corresponding to the respective preset pressures.
[0016] Optionally, determining the first temperature threshold according to the saturation temperature includes:
[0017] Get the preset temperature constant;
[0018] A difference between the saturation temperature and the temperature constant is determined as the first temperature threshold.
[0019] Optionally, determining, according to the current temperature and the first temperature threshold, a region on a preset graph where a state point corresponding to both the current pressure and the current temperature is located includes:
[0020] Determining a second temperature threshold according to the preset chart;
[0021] The region where the state point is located on the preset graph is determined according to the current temperature, the first temperature threshold, and the second temperature threshold.
[0022] Optionally, determining the region where the state point is located on the preset chart according to the current temperature, the first temperature threshold, and the second temperature threshold includes:
[0023] If the current temperature is lower than the first temperature threshold, or the current temperature is lower than the second temperature threshold, determining that the area where the state point is located on the preset chart is a first preset area;
[0024] If the current temperature is greater than or equal to the first temperature threshold, and the current temperature is greater than or equal to the second temperature threshold, the region where the state point is located on the preset graph is determined to be a second preset region.
[0025] Optionally, after determining the area on the preset graph where the state point corresponding to the current pressure and the current temperature is located, the method further includes:
[0026] Marking the position of the state point on the preset chart;
[0027] The area where the state point is located on the preset graph is output.
[0028] In a second aspect, an embodiment of the present application provides a device for determining nuclear power plant accident information, including:
[0029] An information acquisition unit, configured to acquire the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant after determining that the heat transfer tube of the steam generator of the nuclear power plant is broken;
[0030] a temperature threshold determination unit, configured to determine a first temperature threshold according to the current pressure;
[0031] An area determination unit is used to determine the area on a preset chart where the state point corresponding to the current pressure and the current temperature is located based on the current temperature and the first temperature threshold; wherein the preset chart is used to describe the relationship between the pressure of the steam generator and the temperature of the reactor.
[0032] In a third aspect, an embodiment of the present application provides an electronic device, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein when the processor executes the computer program, the processor implements each step of the method for determining nuclear power plant accident information as described in any one of the first aspects above.
[0033] In a fourth aspect, an embodiment of the present application provides a computer-readable storage medium, wherein the computer-readable storage medium stores a computer program, and when the computer program is executed by a processor, each step in the method for determining nuclear power plant accident information as described in any one of the first aspects above is implemented.
[0034] In a fifth aspect, an embodiment of the present application provides a computer program product. When the computer program product is run on a terminal device, the terminal device executes each step of the method for determining nuclear power plant accident information as described in any one of the first aspects above.
[0035] The method, device, equipment and computer program for determining nuclear power plant accident information provided by the embodiments of the present application have the following beneficial effects:
[0036] In the method for determining the accident information of a nuclear power plant provided in the embodiment of the present application, after determining that the heat transfer tube of the steam generator of the nuclear power plant is broken, the electronic device can first obtain the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant, and then determine the first temperature threshold according to the current pressure, and finally determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located according to the current temperature and the first temperature threshold; wherein the preset chart includes a curve for describing the relationship between the pressure of the steam generator and the first temperature threshold. Through this method, the electronic device can automatically determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located. Compared with the existing method of manually reading the current pressure of the steam generator and the current temperature of the reactor, and then checking the area on the preset chart where the state point is located, this method can improve the efficiency of determining the accident information of the nuclear power plant. BRIEF DESCRIPTION OF THE DRAWINGS
[0037] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings required for use in the embodiments or the description of the prior art will be briefly introduced below. 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 creative labor.
[0038] Figure 1 A schematic diagram of a preset chart provided in an embodiment of the present application;
[0039] Figure 2 A flowchart of a method for determining nuclear power plant accident information provided in an embodiment of the present application;
[0040] Figure 3 A schematic diagram of the structure of a device for determining nuclear power plant accident information provided in an embodiment of the present application;
[0041] Figure 4 A schematic diagram of the structure of an electronic device provided in an embodiment of the present application. DETAILED DESCRIPTION
[0042] It should be noted that the terms used in the embodiments of the present application are only used to explain the specific embodiments of the present application, and are not intended to limit the present application. In the description of the embodiments of the present application, unless otherwise specified, "multiple" refers to two or more than two, and "at least one", "one or more" refers to one, two or more. The terms "first" and "second" are only used for descriptive purposes and cannot be understood as indicating or implying relative importance or implicitly indicating the number of indicated technical features. Thus, it is defined that the "first" and "second" features can explicitly or implicitly include one or more of the features.
[0043] References to "one embodiment" or "some embodiments" etc. described in this specification mean that a particular feature, structure or characteristic described in conjunction with the embodiment is included in one or more embodiments of the present application. Thus, the phrases "in one embodiment", "in some embodiments", "in some other embodiments", "in some other embodiments", etc. that appear at different places in this specification do not necessarily refer to the same embodiment, but mean "one or more but not all embodiments", unless otherwise specifically emphasized in other ways. The terms "including", "comprising", "having" and their variations all mean "including but not limited to", unless otherwise specifically emphasized in other ways.
[0044] The execution subject of the method for determining nuclear power plant accident information provided in the embodiment of the present application can be, but is not limited to, electronic devices such as mobile phones, tablet computers, laptop computers, and desktop computers.
[0045] The method for determining nuclear power plant accident information provided in the embodiment of the present application can be applied to a scenario where the state point corresponding to the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant needs to be obtained in the area where the preset chart is located.
[0046] See also Figure 1 , Figure 1 A schematic diagram of a preset chart provided in an embodiment of the present application. Figure 1 As shown, Figure 1 The corresponding preset graph may include a curve for describing the relationship between the pressure of the steam generator and the first temperature threshold. Figure 1 In the corresponding preset chart, the x-axis is used to describe the temperature of the reactor or the temperature corresponding to the first temperature threshold, and the y-axis is used to describe the pressure of the steam generator. The unit corresponding to the x-axis is degrees Celsius, and the unit corresponding to the y-axis is megapascal.
[0047] like Figure 1 As shown, Figure 1 Including Figure ① and Figure ②, Figure ① is an enlarged view of a portion of the curve in the box in the preset chart corresponding to Figure ②, that is, the curve included in the preset chart corresponding to Figure ② is a complete curve, while the curve included in the preset chart corresponding to Figure ① is a partial curve, and the curve included in the preset chart corresponding to Figure ② and the curve included in the preset chart corresponding to Figure ① are used to describe the same curve. It can be seen from Figure ① and Figure ② that when the temperature of the reactor is greater than 255 degrees Celsius or the pressure of the steam generator is greater than 50 MPa, the curve is approximately a straight line.
[0048] In actual applications, after the heat transfer tube of the steam generator of a nuclear power plant ruptures, the personnel of the nuclear power plant need to determine the area on the preset graph where the state point corresponding to the pressure of the steam generator and the temperature of the reactor is located, and then determine whether it is necessary to shut down the injection system.
[0049] In the preset chart, there are usually two areas, such as Figure 1 As shown, the area above the curve is the first area (referred to as area A in practical applications), and the area below the curve is the second area (referred to as area B in practical applications).
[0050] After the heat transfer tube of the steam generator of a nuclear power plant ruptures, the state point corresponding to the pressure of the steam generator and the temperature of the reactor will shift. Specifically, the state point corresponding to the pressure of the steam generator and the temperature of the reactor may be in the first area on the preset graph, or in the second area on the preset graph.
[0051] At present, after a heat transfer tube of a steam generator in a nuclear power plant ruptures, the personnel of the nuclear power plant need to obtain the pressure of the steam generator and the temperature of the reactor, and then determine whether the state point corresponding to the pressure of the steam generator and the temperature of the reactor is in the first area or the second area on the preset graph based on the pressure of the steam generator and the temperature of the reactor. Therefore, it takes a long time to determine the area on the preset graph where the state point corresponding to the pressure of the steam generator and the temperature of the reactor is located, which ultimately reduces the efficiency of determining the accident information of the nuclear power plant.
[0052] Based on this, an embodiment of the present application provides a method for determining nuclear power plant accident information. By executing the various steps of the method for determining nuclear power plant accident information provided by the embodiment of the present application through an electronic device, the electronic device can automatically determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located, thereby improving the efficiency of determining the nuclear power plant accident information.
[0053] See also Figure 2 , Figure 2 This is a flowchart of a method for determining nuclear power plant accident information provided in an embodiment of the present application. The method for determining nuclear power plant accident information provided in an embodiment of the present application may include steps S101 to S103, which are described in detail as follows:
[0054] In S101 , after it is determined that a heat transfer tube of a steam generator of a nuclear power plant is ruptured, the current pressure of the steam generator and the current temperature of a reactor of the nuclear power plant are acquired.
[0055] In the embodiment of the present application, the electronic device can first determine whether the heat transfer tube of the steam generator of the nuclear power plant is broken. The method for the electronic device to determine whether the heat transfer tube of the steam generator of the nuclear power plant is broken can be set according to actual needs and is not limited here.
[0056] After determining that a heat transfer tube of a steam generator of a nuclear power plant is ruptured, the electronic device can obtain the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant.
[0057] Specifically, the electronic device may read the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant from the control system of the nuclear power plant.
[0058] In S102, a first temperature threshold is determined according to the current pressure.
[0059] In the embodiment of the present application, after obtaining the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant, the electronic device may determine the first temperature threshold value according to the obtained current pressure of the steam generator.
[0060] In a possible implementation, the electronic device can determine the first temperature threshold according to the current pressure through steps a and b. The details are as follows:
[0061] In step a, the saturation temperature is determined according to the current pressure and a preset relationship.
[0062] In this implementation, the electronic device may pre-store a preset relationship. After acquiring the current pressure of the steam generator, the electronic device may determine the saturation temperature according to the current pressure and the preset relationship.
[0063] The preset relationship is used to describe the relationship between the current pressure and the saturation temperature.
[0064] In practical applications, the electronic device may determine the preset relationship in the following manner before executing step a. Specifically, the electronic device may first determine the saturation temperatures corresponding to a plurality of preset pressures, and then determine the preset relationship according to the saturation temperatures corresponding to the respective preset pressures.
[0065] In step b, a first temperature threshold is determined according to the saturation temperature.
[0066] In this implementation, after the saturation temperature is determined, the electronic device may determine the first temperature threshold according to the saturation temperature.
[0067] In practical applications, the electronic device may determine the first temperature threshold according to the saturation temperature in the following manner: Specifically, the electronic device may obtain a preset temperature constant, and then determine the difference between the saturation temperature and the temperature constant as the first temperature threshold.
[0068] In practical applications, the preset temperature constant may be determined in advance based on experiments. For example, the temperature constant may be 10 degrees Celsius.
[0069] In S103, according to the current temperature and the first temperature threshold, the region on the preset graph where the state point corresponding to the current pressure and the current temperature is located is determined.
[0070] Therein, a preset chart is used to describe the relationship between the pressure of the steam generator and the temperature of the reactor.
[0071] In an embodiment of the present application, after determining the first temperature threshold, the electronic device can determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located based on the current temperature and the first temperature threshold.
[0072] In a possible implementation, the electronic device can determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located according to the current temperature and the first temperature threshold through step c and step d. The details are as follows:
[0073] In step c, a second temperature threshold is determined according to a preset chart.
[0074] In this implementation, the electronic device may first determine the second temperature threshold according to a preset chart, wherein the second temperature threshold is the temperature corresponding to the starting point of a straight line or curve on the preset chart.
[0075] by Figure 1 Taking the corresponding preset chart as an example, the starting point of the curve on the preset chart is (170, 9). Based on this, the electronic device can Figure 1 The corresponding preset chart determines that the second temperature threshold is 170 degrees Celsius.
[0076] In step d, the region where the state point is located on the preset graph is determined according to the current temperature, the first temperature threshold and the second temperature threshold.
[0077] In this implementation, after the second temperature threshold is determined, the electronic device may determine the area where the state point is located on the preset graph according to the current temperature, the first temperature threshold, and the second temperature threshold.
[0078] Specifically, the electronic device may determine the relationship between the current temperature and the first temperature threshold, and determine the relationship between the current temperature and the second temperature threshold.
[0079] If the electronic device determines that the current temperature is less than the first temperature threshold, or the current temperature is less than the second temperature threshold, the area where the state point is located on the preset chart is determined to be the first preset area.
[0080] If it is determined that the current temperature is greater than or equal to the first temperature threshold, and the current temperature is greater than or equal to the second temperature threshold, then the area where the state point is located on the preset graph is determined to be the second preset area.
[0081] In one possible implementation, after determining the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located, the electronic device can also mark the position of the state point on the preset chart so that the user can obtain the area on the preset chart where the state point is located.
[0082] In another possible implementation, after determining the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located, the electronic device can also output the area on the preset chart where the state point is located, so that the user can obtain the area on the preset chart where the state point is located.
[0083] As can be seen from the above, in the method for determining the accident information of a nuclear power plant provided in the embodiment of the present application, after determining that the heat transfer tube of the steam generator of the nuclear power plant is broken, the electronic device can first obtain the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant, and then determine the first temperature threshold according to the current pressure, and finally determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located according to the current temperature and the first temperature threshold; wherein the preset chart includes a curve for describing the relationship between the pressure of the steam generator and the first temperature threshold. Through this method, the electronic device can automatically determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located. Compared with the existing method of manually reading the current pressure of the steam generator and the current temperature of the reactor, and then checking the area on the preset chart where the state point is located, this method can improve the efficiency of determining the accident information of the nuclear power plant.
[0084] The following Figure 1 Taking the corresponding preset charts as an example, two examples are provided to more clearly describe the various steps of the method for determining nuclear power plant accident information provided in the embodiment of the present application.
[0085] Example 1: If the current pressure of the steam generator obtained by the electronic device is 30 MPa, and the current temperature of the reactor of the nuclear power plant obtained is 200 degrees Celsius, then the electronic device can determine that the saturation temperature corresponding to the current pressure of 30 MPa is 235 Pascal according to the preset relationship. Since in the embodiment of the present application, the preset temperature constant can be 10 degrees Celsius, the first temperature threshold can be 225 degrees Celsius (which is the same as Figure 1 points on the midline curve).
[0086] In addition, Figure 1The starting point of the curve on the corresponding preset graph is (170, 9), so the second temperature threshold is 170 degrees Celsius.
[0087] After determining that the current temperature is 200 degrees Celsius, the first temperature threshold is 225 degrees Celsius, and the second temperature threshold is 170 degrees Celsius, the electronic device can determine the area on the preset chart where the state point corresponding to the current pressure of 30 megapascals and the current temperature of 200 degrees Celsius is located. Specifically, since the current temperature is less than the first temperature threshold, the area on the preset chart where the state point corresponding to the current pressure of 30 megapascals and the current temperature of 200 degrees Celsius is located can be determined as the first preset area.
[0088] Example 2: If the current pressure of the steam generator obtained by the electronic device is 30 MPa, and the current temperature of the reactor of the nuclear power plant obtained is 260 degrees Celsius, then the electronic device can determine that the saturation temperature corresponding to the current pressure of 30 MPa is 235 Pascal according to the preset relationship. Since in the embodiment of the present application, the preset temperature constant can be 10 degrees Celsius, the first temperature threshold can be 225 degrees Celsius (which is the same as Figure 1 points on the midline curve).
[0089] In addition, Figure 1 The starting point of the curve on the corresponding preset graph is (170, 9), so the second temperature threshold is 170 degrees Celsius.
[0090] After determining that the current temperature is 260 degrees Celsius, the first temperature threshold is 225 degrees Celsius, and the second temperature threshold is 170 degrees Celsius, the electronic device can determine the area on the preset chart where the state point corresponding to the current pressure of 30 megapascals and the current temperature of 260 degrees Celsius is located. Specifically, since the current temperature is greater than the first temperature threshold and the current temperature is greater than the second temperature threshold, it can be determined that the area on the preset chart where the state point corresponding to the current pressure of 30 megapascals and the current temperature of 260 degrees Celsius is located is the second preset area.
[0091] It should be noted that determining a suitable temperature constant will have a significant impact on the final result. In practical applications, a suitable temperature constant can be determined based on multiple tests to improve accuracy.
[0092] Based on the method for determining nuclear power plant accident information provided in the above embodiment, the present application further provides a device for determining nuclear power plant accident information that implements the above method embodiment. Figure 3 , Figure 3 This is a schematic diagram of a structure of a device for determining nuclear power plant accident information provided by an embodiment of the present application. Figure 3As shown, the apparatus 30 for determining nuclear power plant accident information may include: an information acquisition unit 31, a temperature threshold determination unit 32, and an area determination unit 33. Among them:
[0093] The information acquisition unit 31 is used to acquire the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant after determining that the heat transfer tube of the steam generator of the nuclear power plant is broken.
[0094] The temperature threshold determination unit 32 is used to determine a first temperature threshold according to the current pressure.
[0095] The area determination unit 33 is used to determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located based on the current temperature and the first temperature threshold; wherein the preset chart includes a curve for describing the relationship between the pressure of the steam generator and the first temperature threshold.
[0096] Optionally, the temperature threshold determination unit 32 is specifically configured to:
[0097] Determine the saturation temperature according to the current pressure and a preset relationship; wherein the preset relationship is used to describe the relationship between the current pressure and the saturation temperature;
[0098] A first temperature threshold is determined according to the saturation temperature.
[0099] Optionally, the nuclear power plant accident information determination device 30 may further include a relationship determination unit.
[0100] The relationship determination unit is specifically used for:
[0101] Determine the saturation temperature corresponding to each of several preset pressures;
[0102] The preset relationship is determined according to the saturation temperatures corresponding to the respective preset pressures.
[0103] Optionally, the temperature threshold determination unit 32 is specifically configured to:
[0104] Get the preset temperature constant;
[0105] The difference between the saturation temperature and the temperature constant is determined as the first temperature threshold.
[0106] Optionally, the region determining unit 33 is specifically configured to:
[0107] Determining a second temperature threshold according to a preset chart;
[0108] The area where the state point is located on the preset graph is determined according to the current temperature, the first temperature threshold, and the second temperature threshold.
[0109] Optionally, the region determining unit 33 is specifically configured to:
[0110] If the current temperature is less than the first temperature threshold, or the current temperature is less than the second temperature threshold, determining that the area where the state point is located on the preset chart is the first preset area;
[0111] If the current temperature is greater than or equal to the first temperature threshold, and the current temperature is greater than or equal to the second temperature threshold, then the area where the state point is located on the preset graph is determined to be the second preset area.
[0112] Optionally, the apparatus 30 for determining nuclear power plant accident information may further include a labeling output unit, wherein:
[0113] The annotation output unit is specifically used for:
[0114] Mark the position of the status point on the preset chart;
[0115] The area where the output status point is located on the preset graph.
[0116] See also Figure 4 , Figure 4 This is a schematic diagram of the structure of an electronic device provided in an embodiment of the present application. Figure 4 As shown, the electronic device 4 provided in this embodiment may include: a processor 40, a memory 41, and a computer program 42 stored in the memory 41 and executable on the processor 40, such as a program corresponding to the method for determining nuclear power plant accident information. When the processor 40 executes the computer program 42, the steps in the embodiment of the method for determining nuclear power plant accident information are implemented, such as Figure 3 Alternatively, when the processor 40 executes the computer program 42, the functions of each module / unit in the above-mentioned embodiment of the apparatus for determining the accident information of a nuclear power plant are realized, for example Figure 3 The functions of the units 31 to 33 are shown.
[0117] Exemplarily, the computer program 42 may be divided into one or more modules / units, one or more modules / units are stored in the memory 41 and executed by the processor 40 to complete the present application. The one or more modules / units may be a series of computer program instruction segments that can complete specific functions, and the instruction segments are used to describe the execution process of the computer program 42 in the electronic device 4. For example, the computer program 42 may be divided into an information acquisition unit 31, a temperature threshold determination unit 32, and an area determination unit 33. For the specific functions of each unit, please refer to Figure 3 The relevant descriptions in the corresponding embodiments are not repeated here.
[0118] Those skilled in the art will understand that Figure 4The electronic device 4 is merely an example and does not limit the electronic device 4 . The electronic device 4 may include more or fewer components than shown in the figure, or may combine certain components, or may include different components.
[0119] The processor 40 may be a central processing unit (CPU), or other general-purpose processors, digital signal processors (DSP), application specific integrated circuits (ASIC), field-programmable gate arrays (FPGA) or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. The general-purpose processor may be a microprocessor or any conventional processor, etc.
[0120] The memory 41 may be an internal storage unit of the electronic device 4, such as a hard disk or memory of the electronic device 4. The memory 41 may also be an external storage device of the electronic device 4, such as a plug-in hard disk, a smart media card (SMC), a secure digital (SD) card, or a flash card, etc., equipped on the electronic device 4. Further, the memory 41 may also include both an internal storage unit and an external storage device of the electronic device 4. The memory 41 is used to store computer programs and other programs and data required by the electronic device. The memory 41 may also be used to temporarily store data that has been output or is to be output.
[0121] The technicians in the relevant field can clearly understand that for the convenience and simplicity of description, only the division of the above-mentioned functional units is used as an example for illustration. In actual applications, the above-mentioned functions can be assigned to different functional units as needed, that is, the internal structure of the device for determining the accident information of a nuclear power plant can be divided into different functional units to complete all or part of the functions described above. The functional units in the embodiment can be integrated into a processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The above-mentioned integrated unit can be implemented in the form of hardware or in the form of software functional units. In addition, the specific names of the functional units are only for the convenience of distinguishing each other, and are not used to limit the scope of protection of this application. The specific working process of the units in the above-mentioned system can refer to the corresponding process in the aforementioned method embodiment, which will not be repeated here.
[0122] An embodiment of the present application further provides a computer-readable storage medium, in which a computer program is stored. When the computer program is executed by a processor, the steps in the above-mentioned method embodiments can be implemented.
[0123] An embodiment of the present application provides a computer program product. When the computer program product is executed on a terminal device, the terminal device implements the steps in the above-mentioned various method embodiments.
[0124] In the above embodiments, the description of each embodiment has its own emphasis. For parts that are not described or recorded in detail in a certain embodiment, reference can be made to the relevant descriptions of other embodiments.
[0125] Those of ordinary skill in the art will appreciate that the units and algorithm steps of each example described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are performed in hardware or software depends on the specific application and design constraints of the technical solution. Professional and technical personnel can use different methods to implement the described functions for each specific application, but such implementation should not be considered to be beyond the scope of this application.
[0126] The embodiments described above are only used to illustrate the technical solutions of the present application, rather than to limit them. Although the present application has been described in detail with reference to the aforementioned embodiments, a person skilled in the art should understand that the technical solutions described in the aforementioned embodiments may still be modified, or some of the technical features may be replaced by equivalents. Such modifications or replacements do not deviate the essence of the corresponding technical solutions from the spirit and scope of the technical solutions of the embodiments of the present application, and should all be included in the protection scope of the present application.
Claims
1. A method for determining nuclear power plant accident information, characterized in that: include: After determining that a heat transfer tube of a steam generator of a nuclear power plant is ruptured, obtaining a current pressure of the steam generator and a current temperature of a reactor of the nuclear power plant; Determining a first temperature threshold according to the current pressure; According to the current temperature and the first temperature threshold, determine the area on the preset chart where the state point corresponding to the current pressure and the current temperature is located; wherein the preset chart includes a curve for describing the relationship between the pressure of the steam generator and the first temperature threshold.
2. The method according to claim 1, characterized in that The determining a first temperature threshold according to the current pressure includes: Determine the saturation temperature according to the current pressure and a preset relationship; wherein the preset relationship is used to describe the relationship between the current pressure and the saturation temperature; The first temperature threshold is determined according to the saturation temperature.
3. The method according to claim 2, characterized in that The preset relationship is determined in the following way: Determining the saturation temperature corresponding to each of a plurality of preset pressures; The preset relationship is determined according to the saturation temperatures corresponding to the respective preset pressures.
4. The method according to claim 2, characterized in that: The determining the first temperature threshold according to the saturation temperature includes: Get the preset temperature constant; A difference between the saturation temperature and the temperature constant is determined as the first temperature threshold.
5. The method according to claim 1, characterized in that The determining, according to the current temperature and the first temperature threshold, a region on a preset graph where a state point corresponding to the current pressure and the current temperature is located includes: Determining a second temperature threshold according to the preset chart; The region where the state point is located on the preset graph is determined according to the current temperature, the first temperature threshold, and the second temperature threshold.
6. The method according to claim 5, characterized in that The determining, according to the current temperature, the first temperature threshold, and the second temperature threshold, the region where the state point is located on the preset graph includes: If the current temperature is lower than the first temperature threshold, or the current temperature is lower than the second temperature threshold, determining that the area where the state point is located on the preset chart is a first preset area; If the current temperature is greater than or equal to the first temperature threshold, and the current temperature is greater than or equal to the second temperature threshold, the region where the state point is located on the preset graph is determined to be a second preset region.
7. The method according to any one of claims 1 to 6, characterized in that: After determining the area on the preset graph where the state point corresponding to the current pressure and the current temperature is located, the method further includes: Marking the position of the state point on the preset chart; The area where the state point is located on the preset graph is output.
8. A device for determining nuclear power plant accident information, characterized in that: include: An information acquisition unit, configured to acquire the current pressure of the steam generator and the current temperature of the reactor of the nuclear power plant after determining that the heat transfer tube of the steam generator of the nuclear power plant is broken; a temperature threshold determination unit, configured to determine a first temperature threshold according to the current pressure; An area determination unit is used to determine the area on a preset chart where the state point corresponding to the current pressure and the current temperature is located based on the current temperature and the first temperature threshold; wherein the preset chart is used to describe the relationship between the pressure of the steam generator and the temperature of the reactor.
9. An electronic device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that: When the processor executes the computer program, each step of the method for determining nuclear power plant accident information as described in any one of claims 1 to 7 is implemented.
10. A computer program, characterized in that When the computer program is executed by a processor, each step of the method for determining nuclear power plant accident information as described in any one of claims 1 to 7 is implemented.