Nuclear power station operation monitoring method and device, electronic equipment and related equipment

Abstract

The invention provides a nuclear power station operation monitoring method and device, electronic equipment and related equipment, and relates to the technical field of nuclear power, and the method comprises the steps: obtaining a limiting parameter of a target object in a nuclear power station, the limiting parameter being used for representing a limiting condition of the operation of the target object during the normal operation of a unit of the nuclear power station; calculating a limit line of the target object based on the limit parameter, wherein the limit line comprises at least one of a temperature limit line and a pressure limit line; monitoring the temperature and / or pressure of the target object based on the limit line; wherein the target object comprises at least one of the following items: a coolant, a main pump in a loop of the nuclear power station, a residual heat removal system, a voltage stabilizer surge pipe and a steam generator. According to the invention, the accuracy of monitoring the temperature or pressure of the primary loop of the nuclear power station during the normal operation period of the unit of the nuclear power station can be improved.

Description

Technical Field

[0001] This invention relates to the field of nuclear power technology, specifically to a method, device, electronic equipment, and related equipment for monitoring the operation of a nuclear power plant. Background Technology

[0002] The primary loop of a nuclear power plant directly transfers heat from the reactor core. Its temperature and pressure must be controlled to prevent safety risks. In relevant technologies, empirical values ​​from experimental tests or practical applications are typically used as limits for temperature and pressure control. However, during normal operation of a nuclear power plant unit, primary loop temperature and pressure fluctuate, sometimes exceeding the specified range. While no abnormality is immediately apparent, monitoring may trigger a false alarm due to inaccurate temperature or pressure control limits.

[0003] It is evident that the relevant technologies suffer from low accuracy in monitoring the temperature or pressure of the primary loop of a nuclear power plant during normal operation of the unit. Summary of the Invention

[0004] This invention provides a method, apparatus, electronic device, and related equipment for monitoring the operation of a nuclear power plant, in order to solve the problem of low accuracy in monitoring the temperature or pressure of the primary loop of a nuclear power plant in related technologies.

[0005] To solve the above problems, the present invention is implemented as follows:

[0006] In a first aspect, embodiments of the present invention provide a method for monitoring the operation of a nuclear power plant, comprising:

[0007] Obtain limiting parameters for a target object in the nuclear power plant, the limiting parameters being used to represent the limiting conditions for the operation of the target object during normal operation of the nuclear power plant units;

[0008] The limiting line of the target object is calculated based on the limiting parameters, and the limiting line includes at least one of a temperature limiting line and a pressure limiting line;

[0009] The temperature and / or pressure of the target object are monitored based on the aforementioned limit line;

[0010] The target object includes at least one of the following:

[0011] Coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer pulsator, and steam generator.

[0012] In one embodiment, when the target object is the coolant, the limiting parameters include a first temperature difference limit, a pressure difference limit, an undersaturation limit, and a preset temperature margin on the primary and secondary sides of the steam generator, and the limiting line is a target undersaturation limiting line, which is used to limit the temperature and pressure of the target object;

[0013] The calculation of the constraint line of the target object based on the constraint parameters includes:

[0014] Obtain the water saturation curve;

[0015] Calculate the initial undersaturation limit line based on the first temperature difference limit, the pressure difference limit, the undersaturation limit, and the saturation curve;

[0016] The initial undersaturation limit line is shifted based on the preset temperature margin to obtain the target undersaturation limit line.

[0017] In one embodiment, the temperature of the coolant in the main pump is higher than the temperature of the primary circuit of the nuclear power plant.

[0018] In one embodiment, when the target object is the main pump, the limiting parameters include the inlet pressure, fluid density, inlet flow rate, and saturation pressure of the main pump, and the limiting line is the pressure limiting line of the main pump;

[0019] The calculation of the constraint line of the target object based on the constraint parameters includes:

[0020] Obtain the target undersaturation limit line;

[0021] Calculate the cavitation margin limit line of the main pump based on the inlet pressure, the fluid density, the inlet flow velocity, and the saturation pressure;

[0022] Based on the target undersaturation limit line and the cavitation margin limit line, the pressure limit line of the main pump is calculated.

[0023] In one embodiment, when the target object is the waste heat removal system, the limiting parameters include a preset upper temperature limit and a preset lower temperature limit, and / or the minimum pressure value, pressure fluctuation value, and measurement uncertainty value of the main pump. The preset upper temperature limit is higher than the primary loop start-up temperature value of the nuclear power plant, the secondary side feedwater temperature value of the steam generator, and the saturation temperature value corresponding to the valve opening setting value of the steam exhaust system.

[0024] The calculation of the constraint line of the target object based on the constraint parameters includes:

[0025] Obtain the target undersaturation limit line;

[0026] Based on the preset upper temperature limit, the preset lower temperature limit, and the target undersaturation limit line, calculate the temperature limit line of the waste heat discharge system; and / or, based on the minimum pressure value of the main pump, the pressure fluctuation value, and the measurement uncertainty value, calculate the minimum pressure value of the waste heat discharge system, and based on the minimum pressure value of the waste heat discharge system and the target undersaturation limit line, calculate the pressure limit line of the waste heat discharge system.

[0027] In one embodiment, when the target object is the pressurizer oscillator, the limiting parameters include a second temperature difference limit between the pressurizer oscillator and the primary loop of the nuclear power plant, a third temperature difference limit between the two ends of the pressurizer oscillator, and the limiting line is the temperature limiting line of the pressurizer oscillator.

[0028] The calculation of the constraint line of the target object based on the constraint parameters includes:

[0029] Obtain the minimum pressure value of the waste heat removal system and the target undersaturation limit line;

[0030] Based on the second temperature difference limit, the third temperature difference limit, and the target undersaturation limit line, calculate the intermediate limit line of the voltage regulator oscillation tube;

[0031] The temperature limit line of the voltage regulator is obtained by deleting the curves in the intermediate limit line that are lower than the minimum pressure value of the waste heat discharge system.

[0032] In one embodiment, when the target object is the steam generator, the limiting parameter includes the pressure difference limit between the primary and secondary sides of the steam generator, and the limiting line is the pressure limiting line of the steam generator;

[0033] The calculation of the constraint line of the target object based on the constraint parameters includes:

[0034] Obtain the target undersaturation limit line;

[0035] Based on the target undersaturation limit line and the differential pressure limit, the pressure limit line of the steam generator is calculated.

[0036] Secondly, embodiments of the present invention also provide a nuclear power plant operation monitoring device, comprising:

[0037] The acquisition module is used to acquire the limiting parameters of the target object in the nuclear power plant, the limiting parameters being used to represent the limiting conditions for the operation of the target object during the normal operation of the nuclear power plant units;

[0038] The calculation module is used to calculate the limit line of the target object based on the limit parameters, wherein the limit line includes at least one of a temperature limit line and a pressure limit line;

[0039] The monitoring module is used to monitor the temperature and / or pressure of the target object based on the limit line;

[0040] The target object includes at least one of the following:

[0041] Coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer pulsator, and steam generator.

[0042] Thirdly, embodiments of the present invention also provide an electronic device, including a processor, a memory, and a computer program stored in the memory and executable on the processor, wherein the computer program, when executed by the processor, implements the steps in the nuclear power plant operation monitoring method described in the first aspect above.

[0043] Fourthly, embodiments of the present invention also provide a computer-readable storage medium storing a computer program, which, when executed by a processor, implements the steps of the nuclear power plant operation monitoring method described in the first aspect above.

[0044] Fifthly, embodiments of the present invention also provide a computer program product, including computer instructions, which, when executed by a processor, implement the steps in the nuclear power plant operation monitoring method described in the first aspect above.

[0045] In this embodiment of the invention, limiting parameters of a target object in a nuclear power plant are obtained. These limiting parameters represent the restrictive conditions for the operation of the target object during normal operation of the nuclear power plant units. Limit lines for the target object are calculated based on these limiting parameters. These limit lines include at least one of temperature and pressure limit lines. The temperature and / or pressure of the target object are monitored based on these limit lines. The target object includes at least one of the following: coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer oscillator, and steam generator. Thus, by determining at least one of the temperature and pressure limit lines for the coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer oscillator, and steam generator using the limiting parameters, the accuracy of the temperature and / or pressure limit lines is improved. Furthermore, by monitoring the temperature and / or pressure of the target object using at least one of the temperature and pressure limit lines, the accuracy of temperature or pressure monitoring in the primary loop of the nuclear power plant during normal operation of the units is improved. Attached Figure Description

[0046] To more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings used in the description of the embodiments of the present invention will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0047] Figure 1 This is a schematic diagram of the primary loop of a nuclear power plant provided in an embodiment of the present invention;

[0048] Figure 2 This is a flowchart of a nuclear power plant operation monitoring method provided in an embodiment of the present invention;

[0049] Figure 3 This is a schematic diagram of the target undersaturation limit line provided in an embodiment of the present invention;

[0050] Figure 4 This is a schematic diagram of the pressure limiting line of the main pump provided in an embodiment of the present invention;

[0051] Figure 5 This is a schematic diagram of the temperature limit line of the voltage regulator oscillator provided in an embodiment of the present invention;

[0052] Figure 6 This is a schematic diagram of the temperature and pressure monitoring graph of a primary loop provided in an embodiment of the present invention;

[0053] Figure 7 This is a structural diagram of a nuclear power plant operation monitoring device provided in an embodiment of the present invention;

[0054] Figure 8 This is a structural diagram of an electronic device provided in an embodiment of the present invention. Detailed Implementation

[0055] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some, not all, of the embodiments of the present invention. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0056] The schematic diagram of the first loop of the nuclear power plant in operation as described in this embodiment of the invention is as follows: Figure 1 As shown, the reactor includes a steam generator 102, a pressurizer 101, a main pump 103, and a waste heat removal system. The coolant is heated as it passes through the pulsating tube of the reactor core 104, and then sequentially passes through the pressurizer 101, the steam generator 102, and the main pump 103 before entering the pulsating tube of the reactor core 104, thus achieving coolant circulation. Specifically, the coolant passes through the pressurizer 101 via the pressurizer pulsating tube.

[0057] The nuclear power plant in this embodiment of the invention includes multiple primary loops, such as... Figure 1 As shown, it includes three primary loops, with waste heat removal systems located between different primary loops, providing auxiliary heat removal. The inlet of the waste heat removal system is located at the hot end of one primary loop (i.e., the port from which the coolant flows out after passing through core 104), and the outlet of the waste heat removal system is located at the cold end of another primary loop (i.e., the port from which the coolant enters core 104).

[0058] The waste heat removal system in this embodiment of the invention includes a coolant pump 105 and a heat exchanger 106 connected in series. The coolant pump 105 is used to provide the flow power for the coolant, and the heat exchanger 106 is used to cool the coolant.

[0059] Please see Figure 2 , Figure 2 This is a flowchart of a nuclear power plant operation monitoring method provided in an embodiment of the present invention, such as... Figure 2 As shown, it includes the following steps:

[0060] Step 201: Obtain the limiting parameters of the target object in the nuclear power plant, wherein the limiting parameters are used to represent the limiting conditions for the operation of the target object during the normal operation of the nuclear power plant units;

[0061] Step 202: Calculate the limit line of the target object based on the limit parameters, wherein the limit line includes at least one of a temperature limit line and a pressure limit line;

[0062] Step 203: Monitor the temperature and / or pressure of the target object based on the limit line;

[0063] The target object includes at least one of the following:

[0064] Coolant, main pumps in the primary loop of the nuclear power plant, residual heat removal system (RHR), pressurizer pulsator, and steam generator.

[0065] In this embodiment of the invention, limiting parameters of a target object in a nuclear power plant are obtained. These limiting parameters represent the restrictive conditions for the operation of the target object during normal operation of the nuclear power plant units. Limit lines for the target object are calculated based on these limiting parameters. These limit lines include at least one of temperature and pressure limit lines. The temperature and / or pressure of the target object are monitored based on these limit lines. The target object includes at least one of the following: coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer oscillator, and steam generator. Thus, by determining at least one of the temperature and pressure limit lines for the coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer oscillator, and steam generator using the limiting parameters, the accuracy of the temperature and / or pressure limit lines is improved. Furthermore, by monitoring the temperature and / or pressure of the target object using at least one of the temperature and pressure limit lines, the accuracy of temperature or pressure monitoring in the primary loop of the nuclear power plant during normal operation of the units is improved.

[0066] In this embodiment of the invention, the coolant passes through various components of the nuclear power plant. Therefore, different components in the nuclear power plant need to meet the temperature and pressure limits of the cold zone to prevent the coolant from boiling or crystallizing. Furthermore, the coolant in this embodiment of the invention can be boron-containing water.

[0067] In this embodiment of the invention, the limiting parameters are parameters of objective limiting conditions that the target object needs to meet. For example, if the target object is a coolant, the coolant in the primary loop cannot boil. Therefore, the limiting parameters are the temperature and pressure parameters that keep the coolant from boiling. In this way, the temperature limit line and / or pressure limit line of the coolant are calculated through the limiting parameters. When the temperature of the coolant meets the temperature limit line and / or the pressure of the coolant meets the pressure limit line, the coolant will not boil, thus satisfying the limiting condition that the coolant in the primary loop cannot boil.

[0068] It should be noted that the limiting parameters are different for different target objects. Before calculating the temperature limit line and / or pressure limit line for different target objects, it is necessary to determine the limiting parameters of the target object, and then calculate the limit line for each target object based on the limiting parameters.

[0069] In this embodiment of the invention, the calculated limit line can be a temperature limit line, a pressure limit line, or both, depending on the nature of the limiting parameters. For example, if the target object is a coolant, the coolant in the primary loop must not boil, so the limit line for the coolant includes both a temperature limit line and a pressure limit line; while if the target object is a waste heat removal system, it is necessary to ensure overpressure protection of the primary loop by the waste heat removal system, and in this case, the calculated limit line is the temperature limit line for the waste heat removal system.

[0070] In one embodiment, when the target object is the coolant, the limiting parameters include a first temperature difference limit, a pressure difference limit, an undersaturation limit, and a preset temperature margin on the primary and secondary sides of the steam generator, and the limiting line is a target undersaturation limiting line, which is used to limit the temperature and pressure of the target object;

[0071] The step of calculating the constraint line of the target object based on the constraint parameters (i.e., step 202) includes:

[0072] Obtain the water saturation curve;

[0073] Calculate the initial undersaturation limit line based on the first temperature difference limit, the pressure difference limit, the undersaturation limit, and the saturation curve;

[0074] The initial undersaturation limit line is shifted based on the preset temperature margin to obtain the target undersaturation limit line.

[0075] It should be noted that the pressurizer in a nuclear power plant controls the primary loop pressure through spraying and electric heating. The upper part contains saturated steam, while the lower part contains unsaturated coolant. The pressure and temperature of this coolant remain on the initial undersaturation curve, thus preventing boiling. The secondary feedwater to the steam generator is heated by the coolant from the primary side through a U-tube, becoming a steam-water mixture. The pressure and temperature of the steam space in the steam generator also remain on the initial undersaturation curve. Since the coolant is boron-containing water, its initial undersaturation limit line is similar to the water saturation curve. The initial undersaturation limit line is calculated by combining the temperature difference limit across the pressurizer's oscillation tube (i.e., the first temperature difference limit), the pressure difference limit between the primary and secondary sides of the steam generator (i.e., the pressure difference limit), and the primary loop coolant undersaturation limit. Specifically, using the water saturation curve as a reference, the shift amount is calculated based on the first temperature difference limit, the pressure difference limit, and the undersaturation limit. This shift amount is then used to shift the water saturation curve, thus obtaining the initial undersaturation limit line.

[0076] During the unit's power operation, the pressurizer contains saturated steam and water, and the secondary side of the steam generator contains a steam-water mixture. Both can be approximated as operating on the saturation curve. When considering the temperature difference limit at both ends of the pressurizer's oscillating tube, the pressure difference limit between the primary and secondary sides of the steam generator, and the undersaturation limit of the coolant, the water saturation curve is also used as the basis. Therefore, the water saturation curve is plotted in the normal operating permit diagram of the primary loop pressure and temperature.

[0077] Furthermore, during normal operation of a nuclear power plant, except for the pressurizer which is a two-phase system, the entire primary loop should be in a solid state of coolant. Nucleation boiling is not permitted throughout the entire process, and the core outlet must not contain vapor. Therefore, at the corresponding operating pressure, the average temperature of the primary loop must maintain sufficient undersaturation to prevent coolant boiling and to avoid localized vaporization at the main pump inlet, which could cause pump cavitation and damage to the pump blades.

[0078] In this embodiment of the invention, a preset temperature margin is used to prevent damage to the blades. The preset temperature margin needs to meet the following conditions:

[0079] a) The undersaturation margin corresponding to the average temperature of the primary loop when the reactor is hot and at zero power should meet the requirements of the formula.

[0080] b) The value of the undersaturation margin in the primary circuit should also be selected to prevent cavitation of the main pump.

[0081] Specifically, in order to meet the saturation requirements of the primary loop, the average temperature T of the primary loop is... avg With the saturation temperature T at the corresponding operating pressure sat The following relationship exists between them:

[0082] T avg ≤T sat -△T const

[0083] Among them, △T const To obtain the target undersaturation limit line, the initial undersaturation limit line is shifted by the preset temperature margin. Figure 3 As shown. The target undersaturation limit line for the primary loop is a leftward shift of ΔT from the initial saturation curve. const The result obtained later is △T const This represents an undersaturation margin. When the undersaturation margin is too large, it intersects with the pressure P0 during power operation at point N. In this case, the operation should be maintained at the primary circuit pressure by increasing the temperature to achieve the hot zero-power real point. From an operational perspective, this is quite difficult, therefore ΔT const It cannot be too large; when △T const When the temperature is low, the thermal safety margin is small, and its safety cannot be guaranteed. Therefore, in this case, the setting of the preset temperature margin should still take into account certain uncertainties.

[0084] Furthermore, the preset temperature margin can be calculated and confirmed based on experimental test data.

[0085] In this embodiment of the invention, an initial undersaturation limit line is calculated based on a first temperature difference limit, a pressure difference limit, an undersaturation limit, and a saturation curve. Then, the initial undersaturation limit line is shifted based on a preset temperature margin to obtain a target undersaturation limit line. The target undersaturation limit line is the limit line for the coolant. When this limit line is met, the coolant will not boil. Thus, the temperature and pressure of the coolant can be monitored through the target undersaturation limit line to prevent the coolant from boiling.

[0086] In one embodiment, the temperature of the coolant in the main pump is higher than the temperature of the primary circuit of the nuclear power plant.

[0087] It should be noted that at least one main pump should be running when the reactor coolant temperature reaches a certain temperature limit to avoid overpressure in the primary loop system caused by starting the first main pump. Before the main pump is started, the main pump shaft seal water supplied by the Chemical and Volume Control System (RCV) enters the primary loop, keeping the temperature inside the main pump casing relatively low. When the coolant temperature in the primary loop is high and the main pump is started, the low-temperature coolant inside the pump casing enters the steam generator and is heated in reverse. At this time, the pressurizer is in a single-phase water state and is very sensitive to temperature-induced volume expansion, which may cause coolant volume expansion and lead to overpressure.

[0088] In this embodiment of the invention, by limiting the temperature of the coolant in the main pump to be higher than the temperature of the primary circuit of the nuclear power plant, the temperature inside the main pump casing cannot be lower than the temperature of the coolant at the cold end, so as to prevent reverse heating by the coolant and avoid overpressure caused by the expansion of the coolant volume.

[0089] Specifically, a temperature limit line can be set for the main pump to operate at, ensuring that the temperature of the coolant inside the main pump is higher than the temperature of the primary circuit in the nuclear power plant.

[0090] In one embodiment, when the target object is the main pump, the limiting parameters include the inlet pressure, fluid density, inlet flow rate, and saturation pressure of the main pump, and the limiting line is the pressure limiting line of the main pump;

[0091] The step of calculating the constraint line of the target object based on the constraint parameters (i.e., step 202) includes:

[0092] Obtain the target undersaturation limit line;

[0093] Calculate the cavitation margin limit line of the main pump based on the inlet pressure, the fluid density, the inlet flow velocity, and the saturation pressure;

[0094] Based on the target undersaturation limit line and the cavitation margin limit line, the pressure limit line of the main pump is calculated.

[0095] It should be noted that cavitation occurs when the head at the main pump inlet is insufficient to maintain fluid flow through the flow channel, and the minimum pressure exceeds the saturated vapor pressure. When cavitation occurs in the main pump, a large number of air bubbles disrupt the continuity of the liquid flow, leading to flow channel blockage, increased flow resistance, and a significant decrease in pump head and efficiency. Furthermore, the high-frequency hydraulic impact following blockage generates localized stress and temperature increases on the surface of the flow channel in contact with the liquid, producing noise and vibration. Combined with the chemical and electrochemical corrosion between the liquid and the component materials, this ultimately results in cavitation damage with sponge-like or honeycomb-like characteristics. Therefore, sufficient cavitation margin (also called net positive suction head) must be maintained during the start-up and operation of the main pump.

[0096] To prevent cavitation in the main pump, the following relationship must be satisfied:

[0097] NPSH a ≥NPSH r

[0098] NPSH a The available NPSH of the main pump (determined by factors such as system configuration and piping layout) r The main pump must have a cavitation margin (provided by the equipment manufacturer, which is related to factors such as pump flow rate).

[0099] The formula for calculating the available cavitation margin of the main pump is as follows:

[0100]

[0101] P i The inlet pressure of the main pump is expressed in Pascals (Pa); ρ is the fluid density, expressed in kilograms per cubic meter (kg / m³). 3 v is the inlet velocity of the main pump, in meters per second (m / s); P sat The saturation pressure is expressed in Pa; g is the acceleration due to gravity, which can be taken as 9.81 m / s². 2 Thus, by calculating the available cavitation margin of the main pump, the available cavitation margin under different pressures is obtained, thereby obtaining the cavitation margin limit line. The cavitation margin limit line is represented by the inlet pressure of the main pump that satisfies the available cavitation margin.

[0102] Furthermore, the relationship between the primary circuit pressure and the main pump inlet pressure is expressed by the following formula:

[0103] P RCP =P i +ΔP LOOP +ΔP SG +ε

[0104] P RCP For the primary circuit pressure, P i The inlet pressure of the main pump, ΔP LOOP The loop pressure loss from the primary hot section pressure gauge to the main pump inlet is ΔP. SG Let ΔP be the pressure loss on the primary side of the steam generator, and ε be the uncertainty in the primary loop pressure measurement. LOOP ΔP SG With ε as a fixed value, and given the inlet pressure of the main pump, let NPSH... a =NPSH r Using the above formula, the relationship between the primary circuit pressure and the primary circuit average temperature can be derived, i.e., the pressure limit line of the main pump, as detailed below. Figure 4 As shown.

[0105] from Figure 4 As can be seen, the pressure limit line of the main pump intersects with the undersaturation limit line of the primary coolant circuit. Assuming the intersection point is S, these two lines together constitute the lower right boundary of the temperature and pressure limit diagram (i.e., the pressure must be greater than the lower right boundary and the pressure limit line of the main pump). Generally, there is a minimum pressure limit for the start-up and operation of the main pump. This limit line cuts off the minimum pressure requirement after the main pump starts up. Therefore, the temperature and pressure operating boundary of the main pump is in the upper left region of the above three lines.

[0106] In this embodiment of the invention, by obtaining the target undersaturation limit line, the cavitation margin limit line of the main pump is calculated based on the inlet pressure, fluid density, inlet velocity and saturation pressure. Then, based on the target undersaturation limit line and the cavitation margin limit line, the pressure limit line of the main pump is calculated.

[0107] In one embodiment, when the target object is the waste heat removal system, the limiting parameters include a preset upper temperature limit and a preset lower temperature limit, and / or the minimum pressure value, pressure fluctuation value, and measurement uncertainty value of the main pump. The preset upper temperature limit is higher than the primary loop start-up temperature value of the nuclear power plant, the secondary side feedwater temperature value of the steam generator, and the saturation temperature value corresponding to the valve opening setting value of the steam exhaust system.

[0108] The step of calculating the constraint line of the target object based on the constraint parameters (i.e., step 202) includes:

[0109] Obtain the target undersaturation limit line;

[0110] Based on the preset upper temperature limit, the preset lower temperature limit, and the target undersaturation limit line, calculate the temperature limit line of the waste heat discharge system; and / or, based on the minimum pressure value of the main pump, the pressure fluctuation value, and the measurement uncertainty value, calculate the minimum pressure value of the waste heat discharge system, and based on the minimum pressure value of the waste heat discharge system and the target undersaturation limit line, calculate the pressure limit line of the waste heat discharge system.

[0111] It should be noted that the waste heat removal system is used when there is excessive heat in the primary loop, and the steam generator cannot consume all of it. This system dissipates the excess heat in the primary loop, preventing heat buildup that could cause the coolant to boil over. In this embodiment of the invention, the waste heat removal system does not operate continuously; it is connected to or disconnected from the primary loop depending on the specific circumstances.

[0112] The access and exit temperatures of the waste heat removal system are related to the following factors: the temperature difference limit between the cold and hot ends of the waste heat removal system heat exchanger; the configuration and operation mode of the steam generator feedwater (start-up and shutdown feedwater system), steam discharge system (steam exhaust system, turbine bypass system), and the heat carrying capacity limit of the secondary side of the steam generator; and the brittle fracture pressure and temperature curve limit at the end of the pressure vessel's service life.

[0113] Specifically, the upper limit of the inlet / outlet temperature of the waste heat removal system is primarily limited by the temperature difference between the cold and hot sides of the heat transfer tubes of the waste heat removal system's heat exchanger. When the cold and hot temperature difference is too large, it will cause a significant thermal shock to the waste heat removal heat exchanger, which may lead to the rupture of the heat transfer tubes. Therefore, it is necessary to avoid an excessively large maximum temperature difference between the cold and hot sides of the waste heat removal heat exchanger, that is, to limit the highest temperature at which the waste heat removal system is connected to the primary loop (i.e., the preset upper limit temperature value).

[0114] Furthermore, to ensure the secondary side of the steam generator has a heating function, before the waste heat removal system is connected to the primary loop, the temperature of the coolant in the primary loop must be higher than the secondary side feedwater temperature of the steam generator during unit startup and shutdown, as well as the saturation temperature corresponding to the valve opening setting value of the steam exhaust system.

[0115] Furthermore, before the waste heat removal system is connected to the primary loop, core heat is removed through the secondary side of the steam generator. However, due to the limited feedwater temperature on the secondary side of the steam generator during unit startup and shutdown, as the primary loop temperature decreases, if the waste heat removal system is not connected in time, the steam generator's heat-carrying capacity will decrease due to the small temperature difference between the primary and secondary sides, potentially failing to meet the unit's normal cooling rate requirements. Simultaneously, since the steam generated by the steam generator during unit startup and shutdown can be discharged through the steam venting system, this steam venting valve has a minimum opening pressure setting. To ensure the steam pressure can open this valve, the steam pressure must not be lower than this setting value. Therefore, it is necessary to limit the temperature at which the waste heat removal system connects to the primary loop to a level that is not too low; otherwise, the steam generated by the steam generator will not be able to open the valve and will not be able to effectively remove heat (i.e., the temperature must not be lower than the preset lower limit).

[0116] Furthermore, when the waste heat removal system is connected to the primary loop, the overpressure protection function of the primary loop is executed by the safety valve of the waste heat removal system; otherwise, the overpressure protection of the primary loop is provided by the safety valve of the pressurizer. The first opening setpoint of the pressurizer's safety valve is significantly higher than the first opening setpoint of the normal waste heat removal system's safety valve. During unit startup or shutdown, as the primary loop temperature rises or falls, if overpressure occurs, the safety valve of the waste heat removal system will provide overpressure protection for the primary loop, posing a risk of brittle fracture to the pressure vessel. Therefore, the lower limit of the waste heat removal system's inlet / outlet temperature should consider the non-ductile fracture failure factors of the pressure vessel, and the inlet / outlet temperature should be as low as possible. The inlet / outlet temperature can be obtained through experimental testing.

[0117] In this embodiment of the invention, a target undersaturation limit line is obtained; the temperature limit line of the waste heat discharge system is calculated based on the preset upper temperature limit value, the preset lower temperature limit value, and the target undersaturation limit line; and / or, the minimum pressure value of the waste heat discharge system is calculated based on the minimum pressure value of the main pump, the pressure fluctuation value, and the measurement uncertainty value, and the pressure limit line of the waste heat discharge system is calculated based on the minimum pressure value of the waste heat discharge system and the target undersaturation limit line.

[0118] In one embodiment, when the target object is the pressurizer oscillator, the limiting parameters include a second temperature difference limit between the pressurizer oscillator and the primary loop of the nuclear power plant, a third temperature difference limit between the two ends of the pressurizer oscillator, and the limiting line is the temperature limiting line of the pressurizer oscillator.

[0119] The calculation of the constraint line of the target object based on the constraint parameters includes:

[0120] Obtain the minimum pressure value of the waste heat removal system and the target undersaturation limit line;

[0121] Based on the second temperature difference limit, the third temperature difference limit, and the target undersaturation limit line, calculate the intermediate limit line of the voltage regulator oscillation tube;

[0122] The temperature limit line of the voltage regulator is obtained by deleting the curves in the intermediate limit line that are lower than the minimum pressure value of the waste heat discharge system.

[0123] It should be noted that the maximum pressure limit of the waste heat removal system connection condition can be used to determine the minimum operating temperature requirement of the primary loop when the voltage regulator is in two-phase operation. The voltage regulator is connected to the primary loop hot section through a surge tube, so the voltage regulator pressure represents the primary loop pressure. Since the primary loop is in an undersaturated state, the temperature of the primary loop coolant is lower than the temperature of the saturated water in the voltage regulator. As a result, the connection point between the voltage regulator surge tube and the primary loop hot section experiences a lower temperature. The temperature difference between the two ends (i.e., the second temperature difference limit) will cause thermal stress in the surge tube. In order to limit the thermal stress in the surge tube and avoid damage to the surge tube, the temperature between the saturated water in the voltage regulator and the primary loop coolant must be limited to a minimum.

[0124] Furthermore, in addition to considering the thermal stress requirements of the pressurizer oscillator tube, the temperature difference requirement at both ends of the pressurizer oscillator tube must also ensure a certain primary loop temperature fluctuation range during unit start-up and shutdown, which is used for the pressurizer to establish and annihilate the steam cavity; and since the pressure control of the primary loop single-phase water solid state is not easy, if it is possible to establish the steam cavity at a lower temperature, the temperature range for the pressurizer to perform pressure control functions can be expanded, which can improve the unit's operational stability and reduce control difficulty.

[0125] Furthermore, the higher the maximum operating pressure of the waste heat removal system connection condition, the higher the saturated water temperature inside the pressurizer during two-phase operation. Given a fixed temperature difference limit across the surge tube (i.e., the third temperature difference limit), the higher the required first loop operating temperature for that condition. To ensure a sufficient primary loop operating temperature range for pressurizer establishment and annihilation chamber operation during unit startup and shutdown under the waste heat removal system connection condition, the maximum pressure of the waste heat removal system connection condition needs to be limited. Specifically, this can be set as a pressure limit line for the waste heat removal system.

[0126] For example, such as Figure 5 As shown, the temperature difference limit line of the pressurizer surge tube will inevitably intersect with the pressure limit line of the waste heat removal system; let's assume the intersection point is K. To meet the temperature difference limit requirements across the pressurizer surge tube, the pressurizer build-up and annihilation chamber should be performed when the primary loop temperature is higher than the temperature corresponding to point K. Therefore, the second temperature difference limit between the pressurizer surge tube and the primary loop of the nuclear power plant, as well as the third temperature difference limit across the pressurizer surge tube (i.e., the third temperature difference limit), determine the primary loop temperature during pressurizer build-up and annihilation chamber operation.

[0127] In this embodiment of the invention, the minimum pressure value and target undersaturation limit line of the waste heat discharge system are obtained; the intermediate limit line of the voltage regulator oscillator is calculated based on the second temperature difference limit, the third temperature difference limit, and the target undersaturation limit line; and the curves in the intermediate limit line that are lower than the minimum pressure value of the waste heat discharge system are deleted to obtain the temperature limit line of the voltage regulator.

[0128] In one embodiment, when the target object is the steam generator, the limiting parameter includes the pressure difference limit between the primary and secondary sides of the steam generator, and the limiting line is the pressure limiting line of the steam generator;

[0129] The calculation of the constraint line of the target object based on the constraint parameters includes:

[0130] Obtain the target undersaturation limit line;

[0131] Based on the target undersaturation limit line and the differential pressure limit, the pressure limit line of the steam generator is calculated.

[0132] It should be noted that due to the limitations of the mechanical strength and stress of the tube sheet of the U-tube in the steam generator, the pressure difference (i.e., the pressure difference limit) between the two sides of the tube sheet (i.e., the primary and secondary sides of the steam generator) must be controlled. When considering the limiting requirements of the pressure difference limit between the primary and secondary sides of the steam generator on the pressure and temperature of the primary circuit during normal operation of the unit, the pressure limit line of the steam generator is calculated based on the assumption that the primary and secondary sides of the steam generator have the same temperature and the secondary side pressure is the saturation pressure corresponding to the operating temperature.

[0133] In some embodiments, during normal unit operation, all control rod assemblies are fully inserted into the reactor core only in maintenance cold shutdown and refueling cold shutdown modes. In residual heat removal system-cooled normal shutdown and above modes, the control rod assemblies are not yet fully inserted into the reactor core. Therefore, during unit startup / shutdown, after leaving the maintenance cold shutdown state and before entering the maintenance cold shutdown state, the control rod drive mechanism must be available to adjust the rod positions according to reactivity control requirements.

[0134] To ensure the usability of the control rod drive mechanism, the pressure housing of the drive unit must be filled with coolant for lubrication. The primary circuit must be maintained at a certain pressure to prevent water from flooding the drive mechanism's pawls if the pressure is too low. This would cause the pawls to lose lubrication and damping, leading to wear and potential malfunction. Therefore, in this embodiment of the invention, a minimum pressure limit line for the primary circuit of the control rod drive mechanism needs to be set, and the minimum pressure of the primary circuit of the control rod drive mechanism must be maintained above this limit line.

[0135] In some embodiments, during maintenance cold shutdown, refueling cold shutdown, and reactor complete unloading shutdown modes, it is necessary to limit the upper limit of the primary loop operating temperature to ensure normal operating conditions for personnel, reduce fogging, and prevent personnel burns.

[0136] In some embodiments, when the unit enters refueling cold shutdown and full unloading shutdown modes, the primary loop is fully open and the operating pressure is atmospheric pressure.

[0137] In some embodiments, the reactor coolant is boron-containing water, and the minimum temperature of the primary coolant is limited to prevent water from freezing and boric acid from crystallizing in the water at low temperatures.

[0138] Embodiments of the present invention also provide, for example Figure 6 The temperature and pressure monitoring graph shown indicates that the monitoring equipment can monitor the temperature and pressure of the primary loop of a nuclear power plant based on the monitoring graph.

[0139] in, Figure 6 Curve 1 is the water saturation curve; curve 2 is the target undersaturation limit line for the coolant; curve 3 is the minimum pressure limit line for main pump startup and operation (i.e., the pressure limit line for the main pump); curve 4 is the effective cavitation limit line for the main pump (i.e., the cavitation margin limit line); curve 5 is the upper limit temperature for the waste heat removal system (i.e., the preset upper limit temperature); curve 6 is the lower limit temperature for the waste heat removal system (i.e., the preset lower limit temperature); curve 7 is the maximum operating pressure limit line for the waste heat removal system (i.e., the pressure limit line for the waste heat removal system); curve 8 is the temperature difference limit line between the two ends of the pressurizer swell tube (i.e., the temperature limit line for the pressurizer); curve 9 is the minimum operating temperature limit line for the main pump; curve 10 is the pressure difference limit line between the primary and secondary sides of the steam generator (i.e., the pressure limit line for the steam generator); curve 11 is the minimum pressure limit line for the primary loop of the control rod drive mechanism; curve 12 is the maximum temperature limit line for cold shutdown during maintenance and refueling; curve 13 is the pressure for cold shutdown during refueling and complete unloading shutdown; and curve 14 is the minimum temperature limit line for the primary loop coolant.

[0140] Please see Figure 7 , Figure 7 This is a structural diagram of a nuclear power plant operation monitoring device provided in an embodiment of the present invention, as shown below. Figure 7 As shown, the nuclear power plant operation monitoring device 700 includes:

[0141] The acquisition module 701 is used to acquire the limiting parameters of the target object in the nuclear power plant, the limiting parameters being used to represent the limiting conditions for the operation of the target object during the normal operation of the nuclear power plant units;

[0142] Calculation module 702 is used to calculate the limit line of the target object based on the limit parameters, wherein the limit line includes at least one of a temperature limit line and a pressure limit line;

[0143] Monitoring module 703 is used to monitor the temperature and / or pressure of the target object based on the limit line;

[0144] The target object includes at least one of the following:

[0145] Coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer pulsator, and steam generator.

[0146] In one embodiment, when the target object is the coolant, the limiting parameters include a first temperature difference limit, a pressure difference limit, an undersaturation limit, and a preset temperature margin on the primary and secondary sides of the steam generator, and the limiting line is a target undersaturation limiting line, which is used to limit the temperature and pressure of the target object;

[0147] The computing module 702 includes:

[0148] The first acquisition unit is used to acquire the water saturation curve;

[0149] The first calculation unit is used to calculate the initial undersaturation limit line based on the first temperature difference limit, the pressure difference limit, the undersaturation limit, and the saturation curve;

[0150] The translation unit is used to translate the initial undersaturation limit line based on the preset temperature margin to obtain the target undersaturation limit line.

[0151] In one embodiment, the temperature of the coolant in the main pump is higher than the temperature of the primary circuit of the nuclear power plant.

[0152] In one embodiment, when the target object is the main pump, the limiting parameters include the inlet pressure, fluid density, inlet flow rate, and saturation pressure of the main pump, and the limiting line is the pressure limiting line of the main pump;

[0153] The computing module 702 includes:

[0154] The second acquisition unit is used to acquire the target undersaturation limit line;

[0155] The second calculation unit is used to calculate the cavitation margin limit line of the main pump based on the inlet pressure, the fluid density, the inlet flow velocity, and the saturation pressure.

[0156] The third calculation unit is used to calculate the pressure limit line of the main pump based on the target undersaturation limit line and the cavitation margin limit line.

[0157] In one embodiment, when the target object is the waste heat removal system, the limiting parameters include a preset upper temperature limit and a preset lower temperature limit, and / or the minimum pressure value, pressure fluctuation value, and measurement uncertainty value of the main pump. The preset upper temperature limit is higher than the primary loop start-up temperature value of the nuclear power plant, the secondary side feedwater temperature value of the steam generator, and the saturation temperature value corresponding to the valve opening setting value of the steam exhaust system.

[0158] The computing module 702 includes:

[0159] The third acquisition unit is used to acquire the target undersaturation limit line;

[0160] The fourth calculation unit is used to calculate the temperature limit line of the waste heat discharge system based on the preset upper temperature limit value, the preset lower temperature limit value, and the target undersaturation limit line; and / or, to calculate the minimum pressure value of the waste heat discharge system based on the minimum pressure value of the main pump, the pressure fluctuation value, and the measurement uncertainty value, and to calculate the pressure limit line of the waste heat discharge system based on the minimum pressure value of the waste heat discharge system and the target undersaturation limit line.

[0161] In one embodiment, when the target object is the pressurizer oscillator, the limiting parameters include a second temperature difference limit between the pressurizer oscillator and the primary loop of the nuclear power plant, a third temperature difference limit between the two ends of the pressurizer oscillator, and the limiting line is the temperature limiting line of the pressurizer oscillator.

[0162] The computing module 702 includes:

[0163] The fourth acquisition unit is used to acquire the minimum pressure value of the waste heat discharge system and the target undersaturation limit line;

[0164] The fifth calculation unit is used to calculate the intermediate limit line of the voltage regulator oscillation tube based on the second temperature difference limit, the third temperature difference limit, and the target undersaturation limit line;

[0165] The deletion unit is used to delete curves in the intermediate limit line that are lower than the minimum pressure value of the waste heat discharge system, so as to obtain the temperature limit line of the voltage regulator.

[0166] In one embodiment, when the target object is the steam generator, the limiting parameter includes the pressure difference limit between the primary and secondary sides of the steam generator, and the limiting line is the pressure limiting line of the steam generator;

[0167] The computing module 702 includes:

[0168] The fifth acquisition unit is used to acquire the target undersaturation limit line;

[0169] The sixth calculation unit is used to calculate the pressure limit line of the steam generator based on the target undersaturation limit line and the differential pressure limit.

[0170] The nuclear power plant operation monitoring device provided in this embodiment of the invention can realize each process of each embodiment of the above-mentioned nuclear power plant operation monitoring method. The technical features are one-to-one and can achieve the same technical effect. To avoid repetition, it will not be described again here.

[0171] It should be noted that the nuclear power plant operation monitoring device in the embodiments of the present invention can be a device, or it can be a component, integrated circuit, or chip in an electronic device.

[0172] This invention also provides an electronic device, see [link to relevant documentation]. Figure 8 , Figure 8 This is a schematic diagram of the structure of an electronic device provided by an embodiment of the present invention. The electronic device includes a memory 801, a processor 802, and a program or instructions stored in the memory 801 that run on the processor 802. When the program or instructions are executed by the processor 802, they can achieve the following: Figure 1 The steps in the corresponding nuclear power plant operation monitoring method embodiments and the achievement of the same beneficial effects will not be repeated here.

[0173] The processor 802 can be a central processing unit (CPU), an application-specific integrated circuit (ASIC), a field-programmable gate array (FPGA), or a complex programmable logic device (CPLD).

[0174] Those skilled in the art will understand that all or part of the steps of the above-described nuclear power plant operation monitoring method embodiments can be implemented by hardware related to program instructions, and the program can be stored in a readable medium.

[0175] This invention also provides a computer-readable storage medium storing a computer program, which, when executed by a processor, can perform the above-described functions. Figure 1 Any step in the corresponding nuclear power plant operation monitoring method embodiment, which can achieve the same technical effect, will not be described again here to avoid repetition. The storage medium mentioned includes, for example, read-only memory (ROM), random access memory (RAM), magnetic disk, or optical disk.

[0176] This invention also provides a computer program product, including computer instructions, which, when executed by a processor, implement the above-described... Figure 1 Any step in the corresponding nuclear power plant operation monitoring method embodiment can achieve the same technical effect, and will not be repeated here to avoid duplication.

[0177] In the embodiments of this invention, the terms "first," "second," etc., are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence. Furthermore, the terms "comprising" and "having," and any variations thereof, are intended to cover non-exclusive inclusion. For example, a process, method, system, product, or device that comprises a series of steps or units is not necessarily limited to those steps or units explicitly listed, but may include other steps or units not explicitly listed or inherent to these processes, methods, products, or devices. Additionally, the use of "and / or" in this application indicates at least one of the connected objects, such as A and / or B and / or C, representing seven possibilities: A alone, B alone, C alone, both A and B present, both B and C present, both A and C present, and A, B, and C present.

[0178] It should be noted that, in this document, the terms "comprising," "including," or any other variations thereof are intended to cover non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements includes not only those elements but also other elements not expressly listed, or elements inherent to such a process, method, article, or apparatus. Unless otherwise specified, an element defined by the phrase "comprising one..." does not exclude the presence of other identical elements in the process, method, article, or apparatus that includes that element.

[0179] Through the above description of the embodiments, those skilled in the art can clearly understand that the methods of the above embodiments can be implemented by means of software plus necessary general-purpose hardware platforms. Of course, they can also be implemented by hardware, but in many cases the former is a better implementation method. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, can be embodied in the form of a software product. This computer software product is stored in a storage medium (such as ROM / RAM, magnetic disk, optical disk) and includes several instructions to cause a terminal (which may be a mobile phone, computer, server, air conditioner, or second terminal device, etc.) to execute the methods of the various embodiments of this application.

[0180] The embodiments of this application have been described above with reference to the accompanying drawings. However, this application is not limited to the specific embodiments described above. The specific embodiments described above are merely illustrative and not restrictive. Those skilled in the art can make many other forms under the guidance of this application without departing from the spirit and scope of the claims, and all of these forms are within the protection scope of this application.

Claims

1. A method for monitoring the operation of a nuclear power plant, characterized in that, include: Obtain limiting parameters for a target object in the nuclear power plant, the limiting parameters being used to represent the limiting conditions for the operation of the target object during normal operation of the nuclear power plant units; The limiting line of the target object is calculated based on the limiting parameters, and the limiting line includes at least one of a temperature limiting line and a pressure limiting line; The temperature and / or pressure of the target object are monitored based on the aforementioned limit line; The target object includes at least one of the following: Coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer pulsator, and steam generator.

2. The method as described in claim 1, characterized in that, When the target object is the coolant, the limiting parameters include the first temperature difference limit, pressure difference limit, undersaturation limit, and preset temperature margin of the primary and secondary sides of the steam generator, and the limiting line is the target undersaturation limiting line, which is used to limit the temperature and pressure of the target object; The calculation of the constraint line of the target object based on the constraint parameters includes: Obtain the water saturation curve; Calculate the initial undersaturation limit line based on the first temperature difference limit, the pressure difference limit, the undersaturation limit, and the saturation curve; The initial undersaturation limit line is shifted based on the preset temperature margin to obtain the target undersaturation limit line.

3. The method as described in claim 2, characterized in that, The temperature of the coolant in the main pump is higher than the temperature of the primary circuit of the nuclear power plant.

4. The method as described in claim 2, characterized in that, When the target object is the main pump, the limiting parameters include the inlet pressure, fluid density, inlet flow rate, and saturation pressure of the main pump, and the limiting line is the pressure limiting line of the main pump; The calculation of the constraint line of the target object based on the constraint parameters includes: Obtain the target undersaturation limit line; Calculate the cavitation margin limit line of the main pump based on the inlet pressure, the fluid density, the inlet flow velocity, and the saturation pressure; Based on the target undersaturation limit line and the cavitation margin limit line, the pressure limit line of the main pump is calculated.

5. The method as described in claim 2, characterized in that, When the target object is the waste heat removal system, the limiting parameters include a preset upper temperature limit and a preset lower temperature limit, and / or the minimum pressure value, pressure fluctuation value, and measurement uncertainty value of the main pump. The preset upper temperature limit is higher than the primary loop start-up temperature value of the nuclear power plant, the secondary side feedwater temperature value of the steam generator, and the saturation temperature value corresponding to the valve opening setting value of the steam exhaust system. The calculation of the constraint line of the target object based on the constraint parameters includes: Obtain the target undersaturation limit line; Based on the preset upper temperature limit, the preset lower temperature limit, and the target undersaturation limit line, calculate the temperature limit line of the waste heat discharge system; and / or, based on the minimum pressure value of the main pump, the pressure fluctuation value, and the measurement uncertainty value, calculate the minimum pressure value of the waste heat discharge system, and based on the minimum pressure value of the waste heat discharge system and the target undersaturation limit line, calculate the pressure limit line of the waste heat discharge system.

6. The method as described in claim 5, characterized in that, When the target object is the pressurizer oscillator, the limiting parameters include a second temperature difference limit between the pressurizer oscillator and the primary loop of the nuclear power plant, a third temperature difference limit between the two ends of the pressurizer oscillator, and the limiting line is the temperature limiting line of the pressurizer oscillator. The calculation of the constraint line of the target object based on the constraint parameters includes: Obtain the minimum pressure value of the waste heat removal system and the target undersaturation limit line; Based on the second temperature difference limit, the third temperature difference limit, and the target undersaturation limit line, calculate the intermediate limit line of the voltage regulator oscillation tube; The temperature limit line of the voltage regulator is obtained by deleting the curves in the intermediate limit line that are lower than the minimum pressure value of the waste heat discharge system.

7. The method as described in claim 2, characterized in that, When the target object is the steam generator, the limiting parameter includes the pressure difference limit between the primary and secondary sides of the steam generator, and the limiting line is the pressure limiting line of the steam generator; The calculation of the constraint line of the target object based on the constraint parameters includes: Obtain the target undersaturation limit line; Based on the target undersaturation limit line and the differential pressure limit, the pressure limit line of the steam generator is calculated.

8. A nuclear power plant operation monitoring device, characterized in that, include: The acquisition module is used to acquire the limiting parameters of the target object in the nuclear power plant, the limiting parameters being used to represent the limiting conditions for the operation of the target object during the normal operation of the nuclear power plant units; The calculation module is used to calculate the limit line of the target object based on the limit parameters, wherein the limit line includes at least one of a temperature limit line and a pressure limit line; The monitoring module is used to monitor the temperature and / or pressure of the target object based on the limit line; The target object includes at least one of the following: Coolant, main pumps in the primary loop of the nuclear power plant, waste heat removal system, pressurizer pulsator, and steam generator.

9. An electronic device, characterized in that, include: A processor, a memory, and a program stored in the memory and executable on the processor, wherein the program, when executed by the processor, implements the steps of the nuclear power plant operation monitoring method as described in any one of claims 1 to 7.

10. A computer-readable storage medium, characterized in that, The computer-readable storage medium stores a computer program that, when executed by a processor, implements the steps of the nuclear power plant operation monitoring method as described in any one of claims 1 to 7.

11. A computer program product, characterized in that, It includes computer instructions that, when executed by a processor, implement the steps of the nuclear power plant operation monitoring method as described in any one of claims 1 to 7.

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