Nuclear reactor power control method and device

Abstract

This application provides a power control method and apparatus for a nuclear reactor, relating to the field of nuclear control. The method includes: acquiring the operating status of a flow meter; acquiring a first main feedwater flow rate of the reactor using an acquisition method corresponding to the operating status; determining a first operating power of the reactor based on the first main feedwater flow rate; and increasing the operating power from the first operating power to a second operating power if the first operating power is less than a first maximum operating power. Wherein, the second operating power is less than or equal to the first maximum operating power, and the sum of the first maximum operating power and a first uncertainty is less than or equal to the reactor's maximum design power. Thus, by determining the current main feedwater flow rate of the reactor based on the main feedwater flow rate measured by the flow meter under normal conditions, the accuracy of the main feedwater flow rate acquisition can be improved, thereby reducing the uncertainty of reactor power acquisition and ultimately increasing the reactor's operating power.

Description

Technical Field

[0001] This invention relates to the field of nuclear control, and more specifically to a power control method and apparatus for a nuclear reactor. Background Technology

[0002] Reactor power is a crucial monitoring parameter during the normal operation of a nuclear power plant. In the composition of reactor power measurement uncertainty, the uncertainty of main feedwater flow rate measurement is the dominant factor, accounting for 80% of the total uncertainty. Currently, nuclear power plants have high uncertainty in main feedwater flow rate measurement, leading to high reactor power measurement uncertainty. Since the maximum design power of the reactor is the sum of the reactor power measurement uncertainty and the maximum operating power, a higher reactor power measurement uncertainty results in a lower reactor operating power. Summary of the Invention

[0003] The purpose of this application is to provide a power control method and apparatus for a reactor, thereby increasing the operating power of the reactor.

[0004] In a first aspect, embodiments of this application provide a power control method for a reactor, applied to a power control device for a reactor. The power control device includes an orifice plate and a flow meter. Both the orifice plate and the flow meter can be used to measure the main feedwater flow rate of the reactor. The main feedwater flow rate is used to determine the operating power of the reactor. The first uncertainty of the operating power determined based on the main feedwater flow rate measured by the flow meter is less than the second uncertainty of the operating power determined based on the main feedwater flow rate measured by the orifice plate.

[0005] Power control methods include:

[0006] Obtain the operating status of the flow meter; the operating status is either faulty or normal.

[0007] The first main feedwater flow rate of the reactor is obtained using a main feedwater flow rate acquisition method corresponding to the operating status; the first main feedwater flow rate is determined based on the main feedwater flow rate of the reactor measured by the flow meter under normal conditions.

[0008] The first operating power of the reactor is determined based on the first main feedwater flow rate;

[0009] If the first operating power is less than the first maximum operating power of the reactor, the operating power of the reactor is increased from the first operating power to the second operating power; the second operating power is less than or equal to the first maximum operating power; the sum of the first maximum operating power and the first uncertainty is less than or equal to the maximum design power of the reactor.

[0010] In some implementations, the first main feedwater flow rate of the reactor is obtained using a main feedwater flow rate acquisition method corresponding to the operating state, including:

[0011] When the flow meter is operating normally, the first main water supply flow rate is obtained by measuring the flow meter.

[0012] In some implementations, the first main feedwater flow rate of the reactor is obtained using a main feedwater flow rate acquisition method corresponding to the operating state, including:

[0013] When the flow meter is in a faulty state, the second main feedwater flow rate of the reactor is obtained by measuring through the orifice plate;

[0014] The first main feedwater flow rate is determined by multiplying the target correction factor by the second main feedwater flow rate; the target correction factor is determined based on the reactor main feedwater flow rate measured by the flow meter under normal conditions.

[0015] In some implementations, before determining the product of the target correction factor and the second main feedwater flow rate as the first main feedwater flow rate, the power control method further includes:

[0016] When the flow meter is in normal operating condition, the third main feedwater flow rate of the reactor measured by the flow meter and the fourth main feedwater flow rate of the reactor measured by the orifice plate are obtained.

[0017] The ratio of the third main water supply flow rate to the fourth main water supply flow rate is determined as the target correction coefficient.

[0018] In some implementations, when the flow meter is in a fault state, after increasing the reactor's operating power from a first operating power to a second operating power, the power control method further includes:

[0019] If the flow meter is in a faulty state for a preset period of time, the fifth main water supply flow rate collected by the orifice plate is obtained;

[0020] The third operating power is determined based on the fifth main water supply flow rate;

[0021] If the third operating power is not equal to the second maximum operating power of the reactor, the operating power of the reactor is adjusted from the third operating power to the fourth operating power; the fourth operating power is less than or equal to the second maximum operating power; the sum of the second maximum operating power and the second uncertainty is less than or equal to the maximum design power of the reactor.

[0022] In some implementations, determining the first operating power of the reactor based on the first main feedwater flow rate includes:

[0023] Obtain the wet steam enthalpy, feedwater enthalpy, blowdown enthalpy, blowdown flow rate, and target heat from the steam generator; the target heat is the heat input to the primary coolant from heat sources other than the reactor.

[0024] The thermal power of the steam generator is determined based on the enthalpy of wet steam, the enthalpy of feedwater, the enthalpy of blowdown, the blowdown flow rate, and the first main feedwater flow rate.

[0025] The difference between thermal power and target heat is determined as the first operating power.

[0026] Secondly, embodiments of this application provide a power control device for a reactor, applied to a power control device for a reactor. The power control device includes an orifice plate and a flow meter. Both the orifice plate and the flow meter can be used to measure the main feedwater flow rate of the reactor. The main feedwater flow rate is used to determine the operating power of the reactor. The first uncertainty of the operating power determined based on the main feedwater flow rate measured by the flow meter is less than the second uncertainty of the operating power determined based on the main feedwater flow rate measured by the orifice plate.

[0027] The power control device includes:

[0028] The first acquisition module is used to acquire the operating status of the flow meter; the operating status is either fault status or normal status.

[0029] The second acquisition module is used to acquire the first main feedwater flow rate of the reactor using a main feedwater flow rate acquisition method corresponding to the operating state; the first main feedwater flow rate is determined based on the main feedwater flow rate of the reactor measured by the flow meter under normal conditions.

[0030] The determination module is used to determine the first operating power of the reactor based on the first main feedwater flow rate;

[0031] The control module is used to increase the reactor's operating power from the first operating power to a second operating power when the first operating power is less than the reactor's first maximum operating power; the second operating power is less than or equal to the first maximum operating power; and the sum of the first maximum operating power and the first uncertainty is less than or equal to the reactor's maximum design power.

[0032] Thirdly, embodiments of this application provide a power control device for a reactor, comprising:

[0033] The memory is configured to store instructions; and

[0034] The processor is configured to retrieve the instructions from the memory and, when executing the instructions, to implement the reactor power control method provided in the first aspect of the embodiments of this application.

[0035] Fourthly, embodiments of this application provide a machine-readable storage medium storing instructions that cause a machine to execute the power control method for a reactor as described above.

[0036] Fifthly, embodiments of this application provide a computer program product in which instructions, when executed by a processor of a reactor power control device, cause the reactor power control device to perform the reactor power control method as described above.

[0037] In this embodiment, firstly, the operating status of the flow meter is acquired; the operating status is either a fault state or a normal state. The first main feedwater flow rate of the reactor is acquired using a main feedwater flow rate acquisition method corresponding to the operating status; the first main feedwater flow rate is determined based on the reactor's main feedwater flow rate measured by the flow meter under normal conditions. Then, the first operating power of the reactor is determined based on the first main feedwater flow rate. If the first operating power is less than the reactor's first maximum operating power, the reactor's operating power is increased from the first operating power to a second operating power. The second operating power is less than or equal to the first maximum operating power, and the sum of the first maximum operating power and the first uncertainty is less than or equal to the reactor's maximum design power. Since the flow meter has a higher accuracy in measuring the main feedwater flow rate than the orifice plate, the uncertainty of the reactor determined based on the main feedwater flow rate measured by the flow meter is lower than that determined based on the main feedwater flow rate measured by the orifice plate. Therefore, by determining the current main feedwater flow rate of the reactor based on the main feedwater flow rate measured by the flow meter under normal conditions, the accuracy of the main feedwater flow rate acquisition can be improved, thereby reducing the uncertainty of the reactor power acquisition and ultimately improving the reactor's operating power. Attached Figure Description

[0038] Figure 1 This is one of the schematic flowcharts of the reactor power control method provided in the embodiments of this application;

[0039] Figure 2 This is a second schematic flowchart of the reactor power control method provided in the embodiments of this application;

[0040] Figure 3 This is a schematic diagram of the reactor power calculation program provided in an embodiment of this application;

[0041] Figure 4 This is a schematic diagram of reactor power enhancement provided in an embodiment of this application;

[0042] Figure 5 This is a schematic diagram of reactor power measurement provided in an embodiment of this application;

[0043] Figure 6 This is a schematic diagram of the power control device for a reactor provided in an embodiment of this application;

[0044] Figure 7 This is a schematic diagram of the power control device for a reactor provided in an embodiment of this application. Detailed Implementation

[0045] The technical solutions of the embodiments of this application will be clearly described below with reference to the accompanying drawings. Obviously, the described embodiments are only some, not all, of the embodiments of this application. All other embodiments obtained by those skilled in the art based on the embodiments of this application are within the scope of protection of this application.

[0046] The terms "first," "second," etc., used in the specification and claims of this application are used to distinguish similar objects and not to describe a specific order or sequence. It should be understood that such terms can be used interchangeably where appropriate so that embodiments of this application can be implemented in orders other than those illustrated or described herein, and the objects distinguished by "first," "second," etc., are generally of the same class and the number of objects is not limited; for example, a first object can be one or more. Furthermore, in the specification and claims, "and / or" indicates at least one of the connected objects, and the character " / " generally indicates that the preceding and following objects are in an "or" relationship.

[0047] The power control method and apparatus for nuclear reactors provided in this application will be described in detail below with reference to the accompanying drawings, through specific embodiments and application scenarios.

[0048] Please see Figure 1 This is one of the flowcharts illustrating a reactor power control method provided in this application embodiment. The method is applied to a reactor power control device. The power control device includes an orifice plate and a flow meter. Both the orifice plate and the flow meter can be used to measure the main feedwater flow rate of the reactor. The main feedwater flow rate is used to determine the reactor's operating power. The accuracy of the main feedwater flow rate measured by the flow meter is higher than that measured by the orifice plate. Therefore, the uncertainty of the main feedwater flow rate measured by the flow meter is less than the uncertainty of the main feedwater flow rate measured by the orifice plate. Consequently, the first uncertainty of the operating power determined based on the main feedwater flow rate measured by the flow meter is less than the second uncertainty of the operating power determined based on the main feedwater flow rate measured by the orifice plate. Figure 1 As shown, the power control method includes the following steps S100 to S400.

[0049] Step S100: Obtain the operating status of the flow meter; the operating status is either fault status or normal status.

[0050] In this embodiment, the reactor power control device may include an orifice plate and a flow meter. Both the orifice plate and the flow meter can be used to measure the main feedwater flow rate of the reactor, and the flow meter has a higher measurement accuracy than the orifice plate. The flow meter has a corresponding main feedwater flow rate acquisition method depending on its operating state. During power control, the operating state of the flow meter is first acquired, which may include a fault state and a normal state. By acquiring the operating state of the flow meter, the main feedwater flow rate acquisition method corresponding to the operating state can be selected, thereby improving the accuracy of power control.

[0051] Step S200: Obtain the first main feedwater flow rate of the reactor using the main feedwater flow rate acquisition method corresponding to the operating state; the first main feedwater flow rate is determined based on the main feedwater flow rate of the reactor measured by the flow meter under normal conditions.

[0052] In this embodiment, after determining the operating state of the flow meter, the first main feedwater flow rate of the reactor is obtained using a main feedwater flow rate acquisition method corresponding to the operating state. The main feedwater flow rate of the reactor refers to the water flow rate required to provide heat exchange for the steam generator or heat exchanger of the nuclear power plant. The first main feedwater flow rate is determined based on the main feedwater flow rate of the reactor measured by the flow meter under normal conditions.

[0053] In this embodiment, when the flow meter is operating normally, the reactor's main feedwater flow rate can be measured by the flow meter. It can be understood that in this case, the first main feedwater flow rate is the current measurement value of the flow meter. When the flow meter is operating in a faulty state, the reactor's main feedwater flow rate can be obtained by correcting the main feedwater flow rate measured by the orifice plate using a target correction factor. The target correction factor is determined based on the main feedwater flow rate measured by the flow meter under normal conditions. It can be understood that in this case, the first main feedwater flow rate is determined based on the historical measurement value of the flow meter under historical normal conditions.

[0054] Step S300: Determine the first operating power of the reactor based on the first main feedwater flow rate.

[0055] In this embodiment, after determining the first main feedwater flow rate, the first operating power of the reactor can be determined based on the first main feedwater flow rate. In one example, the first operating power of the reactor can be determined by calculating the thermal power of the steam generator.

[0056] Step S400: If the first operating power is less than the first maximum operating power of the reactor, the operating power of the reactor is increased from the first operating power to the second operating power; the second operating power is less than or equal to the first maximum operating power; the sum of the first maximum operating power and the first uncertainty is less than or equal to the maximum design power of the reactor.

[0057] In this embodiment, the maximum operating power of the reactor can be understood as the maximum operating power under the premise of safe reactor operation. If the first operating power is less than the first maximum operating power of the reactor, the operating power can be increased from the first operating power to a second operating power. The second operating power is a value less than or equal to the first maximum operating power. If the second operating power equals the first maximum operating power, the reactor can operate at full power at the first maximum operating power.

[0058] In this embodiment, since the maximum design power of the reactor is the sum of the reactor power measurement uncertainty and the maximum operating power of the reactor, and the maximum design power is a fixed value, the maximum operating power of the reactor can be increased by reducing the reactor power measurement uncertainty. In one example, the maximum design power of the reactor is 102%, and the reactor power measurement uncertainty is 2%, then the maximum operating power of the reactor is 100%. By improving the measurement accuracy of the main feedwater flow rate, the reactor power measurement uncertainty is reduced to 0.3%, and the maximum operating power of the reactor can be 101.7%.

[0059] Through steps S100-S400, firstly, the operating status of the flow meter is obtained; the operating status is either a fault state or a normal state. The first main feedwater flow rate of the reactor is obtained using the main feedwater flow rate acquisition method corresponding to the operating status; the first main feedwater flow rate is determined based on the reactor's main feedwater flow rate measured by the flow meter under normal conditions. Then, the first operating power of the reactor is determined based on the first main feedwater flow rate. If the first operating power is less than the reactor's first maximum operating power, the reactor's operating power is increased from the first operating power to a second operating power. Wherein, the second operating power is less than or equal to the first maximum operating power, and the sum of the first maximum operating power and the first uncertainty is less than or equal to the reactor's maximum design power. Since the flow meter has a higher accuracy in measuring the main feedwater flow rate than the orifice plate, the uncertainty of the reactor determined based on the main feedwater flow rate measured by the flow meter is lower than that determined based on the main feedwater flow rate measured by the orifice plate. Therefore, by determining the current main feedwater flow rate of the reactor based on the main feedwater flow rate measured by the flow meter under normal conditions, the accuracy of the main feedwater flow rate acquisition can be improved, thereby reducing the uncertainty of the reactor power acquisition and ultimately improving the reactor's operating power.

[0060] In some implementations, the first main feedwater flow rate of the reactor is obtained using a main feedwater flow rate acquisition method corresponding to the operating state, including:

[0061] When the flow meter is operating normally, the first main water supply flow rate is obtained by measuring the flow meter.

[0062] Specifically, the operating status of the flow meter can include normal status and fault status. When the flow meter is operating in normal status, the first main feedwater flow rate of the reactor can be measured using the flow meter.

[0063] In this embodiment, a flow meter with high accuracy can be selected. In one example, an ultrasonic flow meter can be used. By using a flow meter to measure the first main feedwater flow rate, the accuracy of the main feedwater flow rate measurement can be improved.

[0064] In some implementations, the first main feedwater flow rate of the reactor is obtained using a main feedwater flow rate acquisition method corresponding to the operating state, including:

[0065] When the flow meter is in a faulty state, the second main feedwater flow rate of the reactor is obtained by measuring through the orifice plate;

[0066] The first main feedwater flow rate is determined by multiplying the target correction factor by the second main feedwater flow rate; the target correction factor is determined based on the reactor main feedwater flow rate measured by the flow meter under normal conditions.

[0067] Specifically, when the flow meter is in a faulty state, the first main feedwater flow rate of the reactor can be determined by measuring the second main feedwater flow rate through an orifice plate. It should be noted that "first" and "second" are only used to distinguish objects of the same category and do not limit the number or order of objects.

[0068] In this embodiment, when the flow meter is operating normally, the main feedwater flow rate of the reactor can be measured simultaneously via the flow meter and the orifice plate. The ratio of the main feedwater flow rate measured by the flow meter to the main feedwater flow rate measured by the orifice plate is determined as the target correction coefficient.

[0069] In this embodiment of the application, when correcting the second main feedwater flow rate of the reactor obtained by the orifice plate measurement, the temperature of the second main feedwater flow rate collected by the orifice plate can also be corrected. Then, the reactor operating power can be calculated based on the corrected temperature and the corrected main feedwater flow rate, thereby improving the accuracy of the reactor operating power.

[0070] In this embodiment, the second main feedwater flow rate of the reactor measured by the orifice plate is corrected by multiplying the target correction factor by the second main feedwater flow rate to determine the first main feedwater flow rate. By determining the target correction factor to correct the second main feedwater flow rate measured by the orifice plate, the accuracy of the main feedwater flow rate can be improved.

[0071] In some implementations, before determining the product of the target correction factor and the second main feedwater flow rate as the first main feedwater flow rate, the power control method further includes:

[0072] When the flow meter is in normal operating condition, the third main feedwater flow rate of the reactor measured by the flow meter and the fourth main feedwater flow rate of the reactor measured by the orifice plate are obtained.

[0073] The ratio of the third main water supply flow rate to the fourth main water supply flow rate is determined as the target correction coefficient.

[0074] Specifically, before correcting the reactor's second main feedwater flow rate measured by the orifice plate, a target correction factor needs to be determined. The target correction factor is determined by the reactor's main feedwater flow rate measured by the flowmeter under normal operating conditions. When the flowmeter is operating normally, the reactor's third main feedwater flow rate measured by the flowmeter and the reactor's fourth main feedwater flow rate measured by the orifice plate can be obtained. The reactor's third main feedwater flow rate measured by the flowmeter and the reactor's fourth main feedwater flow rate measured by the orifice plate are measured simultaneously.

[0075] In this embodiment, the ratio of the reactor's third main feedwater flow rate measured by the flowmeter to the reactor's fourth main feedwater flow rate measured by the orifice plate can be determined as the target correction factor. Then, when the flowmeter is in a faulty operating state, the corrected main feedwater flow rate can be obtained by multiplying the main feedwater flow rate measured by the orifice plate by the target correction factor.

[0076] In this embodiment, the value of the target correction coefficient varies according to the changes in the main feedwater flow rate measured by the flow meter and the main feedwater flow rate measured by the orifice plate, rather than being a fixed value.

[0077] In this embodiment, by determining the target correction coefficient, the second main feedwater flow rate measured by the orifice plate can be corrected when the flow meter is in a faulty operating state, thereby improving the accuracy of the main feedwater flow rate.

[0078] In some implementations, when the flow meter is in a fault state, after increasing the reactor's operating power from a first operating power to a second operating power, the power control method further includes:

[0079] If the flow meter is in a faulty state for a preset period of time, the fifth main water supply flow rate collected by the orifice plate is obtained;

[0080] The third operating power is determined based on the fifth main water supply flow rate;

[0081] If the third operating power is not equal to the second maximum operating power of the reactor, the operating power of the reactor is adjusted from the third operating power to the fourth operating power; the fourth operating power is less than or equal to the second maximum operating power; the sum of the second maximum operating power and the second uncertainty is less than or equal to the maximum design power of the reactor.

[0082] Specifically, when the flow meter is in a fault state, the first main feedwater flow rate of the reactor is determined by measuring the main feedwater flow rate through the orifice plate and the target correction coefficient, and the first operating power of the reactor is calculated. After the reactor operating power is increased from the first operating power to the second operating power, and the flow meter is in a fault state for a preset duration, the fifth main feedwater flow rate collected by the orifice plate is acquired, and the third operating power is determined based on the fifth main feedwater flow rate.

[0083] In this embodiment, when the third operating power is not equal to the reactor's second maximum operating power, the reactor's operating power needs to be adjusted from the third operating power to the fourth operating power to ensure the reactor's safe operation. When the third operating power is less than the reactor's second maximum operating power, the reactor's operating power is increased from the third operating power to the fourth operating power; when the third operating power is greater than the reactor's second maximum operating power, the reactor's operating power is decreased from the third operating power to the fourth operating power. The second maximum operating power is less than the first maximum operating power. The fourth operating power is less than or equal to the second maximum operating power; the sum of the second maximum operating power and the second uncertainty is less than or equal to the reactor's maximum design power.

[0084] In this embodiment, because the accuracy of the main feedwater flow rate collected by the orifice plate is relatively low, the safe operation of the reactor can be ensured by reducing the maximum operating power of the reactor when the flow meter is in a faulty state for a preset period of time. In one example, the maximum design power of the reactor is 102%. Since the uncertainty of reactor power measurement increases to 2%, the maximum operating power of the reactor can be reduced to 100%. When the calculated third operating power is less than 100%, the reactor operating power can be increased from the third operating power to the fourth operating power; when the calculated third operating power is greater than 100%, the reactor operating power can be reduced from the third operating power to the fourth operating power. The fourth operating power can be less than 100% or equal to 100%. When the fourth operating power is equal to 100%, the reactor operates at full power (100% of the second maximum operating power).

[0085] In this embodiment of the application, if the operating state of the flow meter changes from a fault state to a normal state within a preset time period, the first main feedwater flow of the reactor will continue to be collected through the flow meter.

[0086] In this embodiment, when the flow meter is in a faulty state for a preset duration, the main feedwater flow rate is collected through an orifice plate, and the operating power is calculated and controlled based on the main feedwater flow rate collected by the orifice plate. Since the accuracy of the main feedwater flow rate collected by the orifice plate is relatively low, the maximum operating power of the reactor is reduced when the flow meter is in a faulty state for the preset duration, thereby ensuring the safe operation of the reactor.

[0087] In some implementations, determining the first operating power of the reactor based on the first main feedwater flow rate includes:

[0088] Obtain the wet steam enthalpy, feedwater enthalpy, blowdown enthalpy, blowdown flow rate, and target heat from the steam generator; the target heat is the heat input to the primary coolant from heat sources other than the reactor.

[0089] The thermal power of the steam generator is determined based on the enthalpy of wet steam, the enthalpy of feedwater, the enthalpy of blowdown, the blowdown flow rate, and the first main feedwater flow rate.

[0090] The difference between thermal power and target heat is determined as the first operating power.

[0091] Specifically, when determining the first operating power of the reactor based on the first main feedwater flow rate, the wet steam enthalpy, feedwater enthalpy, blowdown enthalpy, blowdown flow rate, and target heat of the steam generator can be determined first based on the temperature of the main feedwater flow rate. The target heat can be understood as the heat input to the primary coolant from heat sources other than the reactor. According to the principle of heat balance, the thermal power of the steam generator can be calculated based on the wet steam enthalpy, feedwater enthalpy, blowdown enthalpy, and blowdown flow rate. In one example, the thermal power of the steam generator can be expressed as:

[0092] W SG =(H v -H e )Q e -(H v -H p )Q p

[0093] Among them, W SG H represents the thermal power of the steam generator. v H represents the enthalpy of wet vapor. e Q represents the enthalpy of the feedwater. e H represents the main water supply flow rate. p Q represents the enthalpy value of the wastewater discharge. p This indicates the sewage discharge flow rate.

[0094] The difference between the thermal power and the target thermal power is then determined as the reactor's first operating power. In one example, the first operating power can be expressed as:

[0095]

[0096] Among them, W R This represents the first operating power, and i represents the number of steam generators. Indicates the target heat.

[0097] In this embodiment, the accuracy of the first operating power calculation can be improved by determining the first operating power based on the thermal power of the steam generator and the heat input to the primary coolant from heat sources other than the reactor.

[0098] Please see Figure 2 This is a second schematic flowchart of the reactor power control method provided in the embodiments of this application. Figure 2 As shown, the reactor power control method includes the following steps:

[0099] S201, Obtain the flow meter signal.

[0100] S202, Flow meter fault diagnosis. If the flow meter is faulty, proceed to S203. If the flow meter is normal, proceed to S206.

[0101] S203, power output is switched to reactor power calculation module 2, correction factor remains unchanged from the value before the fault, reactor operates at 101.7% full power.

[0102] S204, determine whether the problem has been repaired within time x. If it has been repaired, proceed to S205; otherwise, proceed to S206.

[0103] S205, power output switched to reactor power calculation module 1, correction coefficient adjusted to 1, reactor reduced to 100% full power operation.

[0104] S206, power output is switched to reactor power calculation module 3 to calculate correction factor, reactor is operating at 101.7% full power.

[0105] In this specific embodiment, a steam generator is used as an example of nuclear power equipment for illustration. For the specific implementation, please refer to the foregoing description, which will not be repeated here.

[0106] Please see Figure 3 This is a schematic diagram of the reactor power calculation program provided in an embodiment of this application. Figure 3 As shown, the reactor power calculation program in this application includes three reactor power calculation modules. Reactor power calculation module 1 calculates the reactor power using the main feedwater flow rate measured by an orifice plate. Reactor power calculation module 3 calculates the reactor power using the main feedwater flow rate measured by an installed flow meter. Reactor power calculation module 2 calculates the reactor power after real-time correction of the main feedwater flow rate measured by the orifice plate.

[0107] In this embodiment, when the flow meter is operating normally, a correction coefficient is determined based on the main feedwater flow rate measured by the orifice plate and the main feedwater flow rate measured by the flow meter. The correction coefficient can be expressed as:

[0108]

[0109] Where, k Q Q represents the correction factor. CSB Q represents the main feedwater flow rate measured by the flow meter. KBF This indicates the main feedwater flow rate measured by the orifice plate.

[0110] After determining the correction factor, in the event of a flow meter failure, the corrected main feedwater flow rate can be determined by multiplying the correction factor by the current main feedwater flow rate measured by the orifice plate.

[0111] In this embodiment, when the flow meter is operating normally, the nuclear power plant uses reactor power calculation module 3 to calculate the reactor power and control it to operate at 101.7% full power. Simultaneously, reactor power calculation module 2 calculates the reactor operating power by real-time correction of the main feedwater flow measured by the orifice plate, ensuring that the output result is equivalent to the reactor operating power calculated by reactor power calculation module 3.

[0112] If the flowmeter is in a fault state, it will switch to fault mode operation. The correction factor of reactor power calculation module 2 will remain unchanged from the value before the fault. The nuclear power plant will calculate the reactor power using reactor power calculation module 2 and continue to operate at 101.7% full power for a period of time (denoted as time x). Time x depends on the flowmeter fault repair time and the degree of drift in orifice plate measurement accuracy during the repair period, and can generally be taken as 2-3 days.

[0113] If the flow meter recovers to normal within x time periods of operation in fault mode, the nuclear power plant will switch back to calculating the reactor power using reactor power calculation module 3 and resume normal operation, with the reactor power controlled at 101.7% full power.

[0114] If the flow meter fails to return to normal after operating in fault mode for more than x hours, the nuclear power plant will switch to calculating the reactor power using reactor power calculation module 1, reducing the reactor power to 100% full power and continuing operation. Once the flow meter returns to normal, the system will switch back to calculating the reactor power using reactor power calculation module 3, restoring normal operation with the reactor power increased to 101.7% full power.

[0115] Please see Figure 4 This is a schematic diagram of reactor power enhancement provided in an embodiment of this application. Figure 4As shown in the embodiments of this application, since the maximum design power of the reactor is the sum of the reactor power measurement uncertainty and the maximum operating power of the reactor, and the maximum design power of the reactor is a fixed value, the maximum operating power of the reactor can be increased by reducing the reactor power measurement uncertainty. Nuclear power plants assume a reactor power measurement uncertainty of 2% and an operating power of 100% full power, and are not allowed to exceed the reactor's maximum design power of 102% full power. After improving the measurement accuracy, assuming the reactor power measurement uncertainty is reduced to 0.3%, the operating power can be increased by 1.7% to 101.7% full power (the application examples below all use this increased power as an assumption), and again, it is not allowed to exceed 102% full power.

[0116] Please see Figure 5 This is a schematic diagram of reactor power measurement provided in an embodiment of this application. Figure 5 As shown, the experimental instrument system uses measured parameters such as the inlet feedwater pressure, temperature, and flow rate of the secondary loop of the steam generator, as well as the main steam pressure and blowdown flow rate, to calculate the enthalpy rise of the working fluid in the secondary loop as it passes through the evaporator. This yields the energy transferred from the primary loop to the secondary loop. Then, taking into account the energy gained and lost by the primary loop through other equipment, the reactor power is calculated using the energy balance principle. Simultaneously, the uncertainty in reactor power measurement also needs to be calculated. Based on the energy balance principle of the primary and secondary loops, the reactor power and the secondary loop power can be expressed as:

[0117]

[0118] Among them, W R Indicates reactor power. This represents the thermal power of a single steam generator, where i represents the number of steam generators. This represents the amount of heat input into the primary coolant from heat sources other than the reactor core.

[0119] Calculate the thermal power of the steam generator based on the principle of energy balance:

[0120] W SG =H v Q v +H p Q p -H e Q e

[0121] Q v =Q e -Q p

[0122] Therefore, we get: W SG =(H v -H e )Qe -(H v -H p )Q p

[0123] Among them, H v H represents the enthalpy of wet vapor. p H represents the enthalpy value of wastewater discharge. e Q represents the enthalpy of the feedwater. v Q represents the wet steam flow rate. p Q represents the sewage discharge flow rate. e Indicates water flow rate.

[0124] The enthalpy of wet vapor can be obtained through the following relationship: H v =xH vs +(1-x)H es

[0125] Among them, H vs H represents the enthalpy of saturated vapor. es represents the enthalpy of saturated water, and x represents the dryness of the steam generator outlet.

[0126] In this embodiment, the enthalpy of the wastewater discharge corresponds to the enthalpy of saturated water at the SG outlet pressure. The enthalpy of the saturated state is calculated using a water meter based on the measured SG outlet pressure. The enthalpy of the feedwater is calculated using a water meter based on the measured feedwater pressure and temperature.

[0127] Based on the above principle of heat balance, the reactor power can be calculated:

[0128]

[0129] Based on the heat balance calculations, the reactor measurement uncertainty can be expressed as:

[0130]

[0131] Among them, U(W SG1 ), U(W SG2 ), U(W SG3 U(W) represents the uncertainty in the thermal power measurement of the first steam generator, the second steam generator, and the third steam generator, respectively. ΔPR U(W) represents the measurement uncertainty of other input power terms. R ) represents the measurement uncertainty of reactor power.

[0132] Please see Figure 6This is a schematic diagram of the structure of a reactor power control device provided in an embodiment of this application. It is applied to a reactor power control device, which includes an orifice plate and a flow meter. Both the orifice plate and the flow meter can be used to measure the main feedwater flow rate of the reactor. The main feedwater flow rate is used to determine the reactor's operating power. The first uncertainty of the operating power determined based on the main feedwater flow rate measured by the flow meter is less than the second uncertainty of the operating power determined based on the main feedwater flow rate measured by the orifice plate. A second aspect of this application provides a reactor power control device 60, which includes:

[0133] The first acquisition module 61 is used to acquire the operating status of the flow meter; the operating status is either fault status or normal status.

[0134] The second acquisition module 62 is used to acquire the first main feedwater flow rate of the reactor using a main feedwater flow rate acquisition method corresponding to the operating state; the first main feedwater flow rate is determined based on the main feedwater flow rate of the reactor measured by the flow meter under normal conditions.

[0135] Module 63 is used to determine the first operating power of the reactor based on the first main feedwater flow rate;

[0136] The control module 64 is used to increase the reactor's operating power from the first operating power to a second operating power when the first operating power is less than the reactor's first maximum operating power; the second operating power is less than or equal to the first maximum operating power; and the sum of the first maximum operating power and the first uncertainty is less than or equal to the reactor's maximum design power.

[0137] The power control device 60 provided in the second aspect of the embodiments of this application can implement the various processes implemented in the above method embodiments and achieve the same beneficial effects. To avoid repetition, it will not be described again here.

[0138] Please see Figure 7 This is a schematic diagram of the structure of a reactor power control device provided in an embodiment of this application. A third aspect of this application provides a reactor power control device 7000, including a processor 7100 and a memory 7200. The memory 7200 stores machine-executable instructions that can be executed by the processor 7100. The processor 7100 can execute the machine-executable instructions to implement the above-mentioned reactor power control method.

[0139] In some embodiments, this application also provides a machine-readable storage medium storing instructions that, when executed by a processor, cause the processor to implement the above-described reactor power control method.

[0140] In some embodiments, this application also provides a computer program product, including a computer program that, when executed by a processor, implements the reactor power control method according to the above embodiments.

[0141] Those skilled in the art will understand that embodiments of this application can be provided as methods, systems, or computer program products. Therefore, this application can take the form of a completely hardware embodiment, a completely software embodiment, or an embodiment combining software and hardware aspects. Furthermore, this application can take the form of a computer program product embodied on one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) containing computer-usable program code.

[0142] This application is described with reference to flowchart illustrations and / or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of this application. It will be understood that each block of the flowchart illustrations and / or block diagrams, and combinations of blocks in the flowchart illustrations and / or block diagrams, can be implemented by computer program instructions. These computer program instructions can be provided to a processor of a general-purpose computer, special-purpose computer, embedded processor, or other programmable data processing apparatus to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing apparatus, generate instructions for implementing the flowchart... Figure 1 One or more processes and / or boxes Figure 1 The computer program instructions may also be stored in a computer-readable storage medium that can direct a computer or other programmable data processing device to function in a particular manner, such that the instructions stored in the computer-readable storage medium produce an article of manufacture including instruction means, which are implemented in a process Figure 1 One or more processes and / or boxes Figure 1 The functions specified in one or more boxes. These computer program instructions may also be loaded onto a computer or other programmable data processing apparatus to cause a series of operational steps to be performed on the computer or other programmable apparatus to produce a computer-implemented process, thereby providing instructions that execute on the computer or other programmable apparatus for implementing the process. Figure 1 One or more processes and / or boxes Figure 1 The steps of the function specified in one or more boxes.

[0143] In a typical configuration, a computing device includes one or more processors (CPU), input / output interfaces, network interfaces, and memory.

[0144] Memory may include non-persistent memory in computer-readable media, such as random access memory (RAM) and / or non-volatile memory, such as read-only memory (ROM) or flash RAM. Memory is an example of computer-readable media.

[0145] Computer-readable media includes both permanent and non-permanent, removable and non-removable media that can store information using any method or technology. Information can be computer-readable instructions, data structures, modules of programs, or other data. Examples of computer storage media include, but are not limited to, phase-change memory (PRAM), static random access memory (SRAM), dynamic random access memory (DRAM), other types of random access memory (RAM), read-only memory (ROM), electrically erasable programmable read-only memory (EEPROM), flash memory or other memory technologies, CD-ROM, digital versatile optical disc (DVD) or other optical storage, magnetic tape, magnetic magnetic disk storage or other magnetic storage devices, or any other non-transferable medium that can be used to store information accessible by a computing device. As defined herein, computer-readable media does not include transient computer-readable media, such as modulated data signals and carrier waves.

[0146] It should also be noted that the terms "comprises," "includes," or any other variations thereof are intended to encompass non-exclusive inclusion, such that a process, method, commodity, or apparatus that includes a series of elements includes not only those elements but also other elements not explicitly listed, or includes elements inherent to such process, method, commodity, or apparatus. In the absence of further limitations, an element defined by the phrase "comprises a ..." does not exclude the presence of other identical elements in the process, method, commodity, or apparatus that includes the element.

[0147] The above are merely embodiments of this application and are not intended to limit the scope of this application. Various modifications and variations can be made to this application by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of this application should be included within the scope of the claims of this application.

[0148] Furthermore, various different embodiments of the present invention can be combined in any way, as long as they do not violate the spirit of the present invention, they should also be regarded as the content disclosed by the present invention.

Claims

1. A power control method for a nuclear reactor, characterized in that, A power control device for a reactor, comprising an orifice plate and a flow meter, both of which can be used to measure the main feedwater flow rate of the reactor, the main feedwater flow rate being used to determine the operating power of the reactor; wherein, a first uncertainty in the operating power determined based on the main feedwater flow rate measured by the flow meter is less than a second uncertainty in the operating power determined based on the main feedwater flow rate measured by the orifice plate; The power control method includes: Obtain the operating status of the flow meter; the operating status is either a fault state or a normal state. The first main feedwater flow rate of the reactor is obtained using a main feedwater flow rate acquisition method corresponding to the operating state; the first main feedwater flow rate is determined based on the main feedwater flow rate of the reactor measured by the flow meter under normal conditions. The first operating power of the reactor is determined based on the first main feedwater flow rate; If the first operating power is less than the first maximum operating power of the reactor, the operating power of the reactor is increased from the first operating power to a second operating power; the second operating power is less than or equal to the first maximum operating power; the sum of the first maximum operating power and the first uncertainty is less than or equal to the maximum design power of the reactor; The step of obtaining the first main feedwater flow rate of the reactor using a main feedwater flow rate acquisition method corresponding to the operating state includes: When the flow meter is in a faulty state, the second main feedwater flow rate of the reactor is measured through the orifice plate; The first main feedwater flow rate is determined by multiplying the target correction factor by the second main feedwater flow rate; the target correction factor is determined based on the reactor's main feedwater flow rate measured by the flow meter under normal conditions.

2. The power control method according to claim 1, characterized in that, Before determining the product of the target correction coefficient and the second main water flow rate as the first main water flow rate, the power control method further includes: When the flow meter is in normal operating condition, the third main feedwater flow rate of the reactor measured by the flow meter and the fourth main feedwater flow rate of the reactor measured by the orifice plate are obtained. The ratio of the third main water supply flow rate to the fourth main water supply flow rate is determined as the target correction coefficient.

3. The power control method according to claim 1, characterized in that, When the flow meter is in a fault state, after increasing the reactor's operating power from the first operating power to the second operating power, the power control method further includes: If the flow meter is in a faulty state for a preset period of time, the fifth main water flow rate collected by the orifice plate is obtained; The third operating power is determined based on the fifth main water supply flow rate; If the third operating power is not equal to the second maximum operating power of the reactor, the operating power of the reactor is adjusted from the third operating power to the fourth operating power; the fourth operating power is less than or equal to the second maximum operating power; the sum of the second maximum operating power and the second uncertainty is less than or equal to the maximum design power of the reactor.

4. The power control method according to claim 1, characterized in that, The step of determining the first operating power of the reactor based on the first main feedwater flow rate includes: The wet steam enthalpy, feedwater enthalpy, blowdown enthalpy, blowdown flow rate, and target heat value of the steam generator are obtained; the target heat value is the heat input to the primary coolant from heat sources other than the reactor. The thermal power of the steam generator is determined based on the wet steam enthalpy, the feedwater enthalpy, the blowdown enthalpy, the blowdown flow rate, and the first main feedwater flow rate. The difference between the thermal power and the target heat is determined as the first operating power.

5. A power control device for a reactor, characterized in that, A power control device for a reactor, comprising an orifice plate and a flow meter, both of which can be used to measure the main feedwater flow rate of the reactor, the main feedwater flow rate being used to determine the operating power of the reactor; wherein, a first uncertainty in the operating power determined based on the main feedwater flow rate measured by the flow meter is less than a second uncertainty in the operating power determined based on the main feedwater flow rate measured by the orifice plate; The power control device includes: The first acquisition module is used to acquire the operating status of the flow meter; the operating status is either a fault state or a normal state. The second acquisition module is used to acquire the first main feedwater flow rate of the reactor using a main feedwater flow rate acquisition method corresponding to the operating state; the first main feedwater flow rate is determined based on the main feedwater flow rate of the reactor measured by the flow meter under normal conditions. The determination module is used to determine the first operating power of the reactor based on the first main feedwater flow rate; The control module is configured to increase the operating power of the reactor from the first operating power to a second operating power when the first operating power is less than the first maximum operating power of the reactor; the second operating power is less than or equal to the first maximum operating power; and the sum of the first maximum operating power and the first uncertainty is less than or equal to the maximum design power of the reactor. The second acquisition module is further configured to measure the second main feedwater flow rate of the reactor through the orifice plate when the flow meter is in a fault state; and to determine the first main feedwater flow rate by multiplying the target correction coefficient by the second main feedwater flow rate; the target correction coefficient is determined based on the main feedwater flow rate of the reactor measured by the flow meter in the normal state.

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