Reactor power control method, device, equipment, medium and product

Abstract

The invention provides a power control method, device and equipment of a reactor, a medium and a product, and relates to the field of nuclear control. The method comprises the steps of obtaining the running state of the flowmeter; and acquiring the first main feed water flow of the reactor by adopting an acquisition mode corresponding to the operation state. And determining the first operation power of the reactor according to the first main feed water flow. If the first operating power is less than the first maximum operating power, the operating power is increased from the first operating power to the second operating power. Wherein the second operation power is smaller than or equal to the first maximum operation power, and the sum of the first maximum operation power and the first uncertainty is smaller than or equal to the maximum design power of the reactor. Thus, the current main feed water flow of the reactor is determined based on the main feed water flow of the reactor measured by the flowmeter in the normal state, the accuracy of obtaining the main feed water flow can be improved, the uncertainty of obtaining the power of the reactor can be reduced, and then the operation power of the reactor is improved.

Description

Technical Field

[0001] The present invention relates to the field of nuclear control, and in particular to a method, device, equipment, medium and product for controlling power of a reactor. Background Art

[0002] Reactor power is an important monitoring parameter during the normal operation of a nuclear power plant. Among the uncertainty components of reactor power measurement, the uncertainty of main feedwater flow measurement is the dominant factor, accounting for 80% of the total uncertainty. The uncertainty of main feedwater flow measurement in current nuclear power plants is high, resulting in high uncertainty in reactor power measurement. Since the maximum design power of the reactor is the sum of the uncertainty of reactor power measurement and the maximum operating power of the reactor, when the uncertainty of reactor power measurement is high, the operating power of the reactor is low. Summary of the invention

[0003] The purpose of the embodiments of the present application is to provide a method, device, equipment, medium and product for power control of a reactor, so as to improve the operating power of the reactor.

[0004] In a first aspect, an embodiment of the present application provides a power control method for a reactor, which is applied to a power control device of the reactor, wherein the power control device includes an orifice plate and a flow meter, and both the orifice plate and the flow meter can be used to measure the main feed water flow of the reactor, and the main feed water flow is used to determine the operating power of the reactor; wherein a first uncertainty of the operating power determined based on the main feed water flow measured by the flow meter is less than a second uncertainty of the operating power determined based on the main feed water flow measured by the orifice plate;

[0005] Power control methods include:

[0006] Get the running status of the flow meter; the running status is a fault state or a normal state;

[0007] A first main feed water flow rate of the reactor is obtained by adopting a main feed water flow rate acquisition method corresponding to the operating state; the first main feed water flow rate is determined based on the main feed water flow rate of the reactor measured by the flow meter under normal conditions;

[0008] determining a first operating power of the reactor according to the first main feedwater flow rate;

[0009] When 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 embodiments, obtaining a first main feed water flow rate of a reactor by adopting a main feed water flow rate obtaining method corresponding to an operating state includes:

[0011] When the operating state of the flow meter is normal, the first main water supply flow rate is measured by the flow meter.

[0012] In some embodiments, obtaining a first main feed water flow rate of a reactor by adopting a main feed water flow rate obtaining method corresponding to an operating state includes:

[0013] When the running state of the flow meter is a fault state, the second main feed water flow rate of the reactor is measured through the orifice plate;

[0014] The product of the target correction coefficient and the second main feed water flow rate is determined as the first main feed water flow rate; the target correction coefficient is determined based on the main feed water flow rate of the reactor measured by the flow meter under normal conditions.

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

[0016] When the operation state of the flow meter is normal, obtaining the third main feed water flow rate of the reactor measured by the flow meter and the fourth main feed water flow rate of the reactor measured by the orifice plate;

[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 embodiments, when the operating state of the flow meter is a fault state, after increasing the operating power of the reactor from the first operating power to the second operating power, the power control method further includes:

[0019] When the duration of the flow meter being in a fault state reaches a preset duration, obtaining the fifth main water supply flow rate collected by the orifice plate;

[0020] determining a third operating power according to a fifth main feedwater flow rate;

[0021] When 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 embodiments, determining a first operating power of the reactor according to the first main feedwater flow rate includes:

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

[0024] Determining the thermal power of the steam generator according to the wet steam enthalpy, the feed water enthalpy, the blowdown enthalpy, the blowdown flow rate, and the first main feed water flow rate;

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

[0026] In a second aspect, an embodiment of the present application provides a power control device for a reactor, which is applied to a power control device of a reactor, wherein the power control device includes an orifice plate and a flow meter, wherein both the orifice plate and the flow meter can be used to measure the main feed water flow of the reactor, and the main feed water flow is used to determine the operating power of the reactor; wherein a first uncertainty of the operating power determined based on the main feed water flow measured by the flow meter is less than a second uncertainty of the operating power determined based on the main feed water flow measured by the orifice plate;

[0027] The power control device includes:

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

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

[0030] A determination module, used for determining a first operating power of the reactor according to a first main feedwater flow rate;

[0031] A control module is used to increase the operating power of the reactor from a 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.

[0032] In a third aspect, an embodiment of the present application provides a power control device for a reactor, comprising:

[0033] a memory configured to store instructions; and

[0034] The processor is configured to call the instructions from the memory and implement the power control method of the reactor provided in the first aspect of the embodiment of the present application when executing the instructions.

[0035] In a fourth aspect, an embodiment of the present application provides a machine-readable storage medium, on which instructions are stored, and the instructions are used to enable a machine to execute the power control method of the reactor according to the above-mentioned method.

[0036] In a fifth aspect, an embodiment of the present application provides a computer program product. When the instructions in the computer program product are executed by a processor of a power control device of a reactor, the power control device of the reactor executes the power control method of the reactor as described above.

[0037] In an embodiment of the present application, first, the operating state of the flow meter is obtained; the operating state is a fault state or a normal state. The first main feed water flow of the reactor is obtained by adopting a main feed water flow acquisition method corresponding to the operating state; the first main feed water flow is determined based on the main feed water flow of the reactor measured by the flow meter under normal conditions. Then, the first operating power of the reactor is determined according to the first main feed water flow. When 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. Among them, 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. Since the measurement accuracy of the main feed water flow by the flow meter is higher than that of the orifice plate, the uncertainty of the reactor determined based on the main feed water flow measured by the flow meter is lower than the uncertainty of the reactor determined based on the main feed water flow measured by the orifice plate. In this way, by determining the current main feed water flow of the reactor based on the main feed water flow of the reactor measured by the flow meter under normal conditions, the accuracy of obtaining the main feed water flow can be improved, thereby reducing the uncertainty of obtaining the reactor power, and then improving the operating power of the reactor. BRIEF DESCRIPTION OF THE DRAWINGS

[0038] Figure 1 It is one of the flow diagrams of the power control method of the reactor provided in the embodiment of the present application;

[0039] Figure 2 This is the second flow chart of the power control method of the reactor provided in the embodiment of the present application;

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

[0041] Figure 4 It is a schematic diagram of reactor power enhancement provided by an embodiment of the present application;

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

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

[0044] Figure 7 It is a schematic diagram of the structure of the power control device of the reactor provided in the embodiment of the present application. DETAILED DESCRIPTION

[0045] The following will be combined with the drawings in the embodiments of the present application to clearly describe the technical solutions in the embodiments of the present application. Obviously, the described embodiments are part of the embodiments of the present application, rather than all the embodiments. All other embodiments obtained by ordinary technicians in this field based on the embodiments in the present application belong to the scope of protection of this application.

[0046] The terms "first", "second", etc. in the specification and claims of the present application are used to distinguish similar objects, and are not used to describe a specific order or sequence. It should be understood that the terms used in this way are interchangeable where appropriate, so that the embodiments of the present application can be implemented in an order other than those illustrated or described herein, and the objects distinguished by "first", "second", etc. are generally of one type, and the number of objects is not limited. For example, the first object can be one or more. In addition, "and / or" in the specification and claims represents at least one of the connected objects, and the character " / " generally indicates that the objects associated with each other are in an "or" relationship.

[0047] The power control method, device, equipment, medium and product of the reactor provided in the embodiments of the present application are described in detail below with reference to the accompanying drawings through specific embodiments and their application scenarios.

[0048] See also Figure 1 , is one of the flow charts of the power control method of the reactor provided in the embodiment of the present application, and the method is applied to the power control equipment of the reactor. The power control equipment includes an orifice plate and a flow meter, both of which can be used to measure the main feed water flow of the reactor, and the main feed water flow is used to determine the operating power of the reactor; wherein, the accuracy of the main feed water flow measured by the flow meter is higher than the accuracy of the main feed water flow measured by the orifice plate, therefore, the uncertainty of the main feed water flow measured by the flow meter is smaller than the uncertainty of the main feed water flow measured by the orifice plate, and further, the first uncertainty of the operating power determined based on the main feed water flow measured by the flow meter is smaller than the second uncertainty of the operating power determined based on the main feed water flow measured by the orifice plate. As Figure 1 As shown, the power control method includes the following steps S100 to S400.

[0049] Step S100: Acquire the operating state of the flow meter; the operating state is a fault state or a normal state.

[0050] In an embodiment of the present application, the power control device of the reactor may include an orifice plate and a flow meter, both of which can be used to measure the main feed water flow of the reactor, and the measurement accuracy of the flow meter is higher than that of the orifice plate. When the flow meter is in different operating states, there is a corresponding method for obtaining the main feed water flow. When performing power control, the operating state of the flow meter is first obtained, and the operating state may include a fault state and a normal state. By obtaining the operating state of the flow meter, the method for obtaining the main feed water flow corresponding to the operating state can be selected, thereby improving the accuracy of power control.

[0051] Step S200: acquiring a first main feed water flow rate of the reactor by adopting a main feed water flow rate acquisition method corresponding to the operating state; the first main feed water flow rate is determined based on the main feed water flow rate of the reactor measured by a flow meter under normal conditions.

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

[0053] In the embodiment of the present application, when the operating state of the flow meter is normal, the main feed water flow rate of the reactor can be measured by the flow meter, and it can be understood that in this case, the first main feed water flow rate is the current measurement value of the flow meter. When the operating state of the flow meter is a fault state, the main feed water flow rate of the reactor can be obtained by correcting the main feed water flow rate measured by the orifice plate by a target correction coefficient, and the target correction coefficient is determined based on the main feed water flow rate measured by the flow meter in a normal state. It can be understood that in this case, the first main feed water flow rate is determined based on the historical measurement value of the flow meter in a historical normal state.

[0054] Step S300: determining a first operating power of the reactor according to the first main feed water flow rate.

[0055] In the embodiment of the present application, after determining the first main feedwater flow rate, the first operating power of the reactor can be determined according to 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: When 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 the embodiment of the present application, the maximum operating power of the reactor can be understood as the maximum value of the operating power under the premise of safe operation of the reactor. When the first operating power is less than the first maximum operating power of the reactor, the operating power of the reactor can be increased from the first operating power to the second operating power. The second operating power is a value less than or equal to the first maximum operating power. When the second operating power is equal to the first maximum operating power, the reactor can operate at full power at the first maximum operating power.

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

[0059] Through the above steps S100-S400, first, the operating state of the flow meter is obtained; the operating state is a fault state or a normal state. The first main feed water flow of the reactor is obtained by adopting the main feed water flow acquisition method corresponding to the operating state; the first main feed water flow is determined based on the main feed water flow of the reactor measured by the flow meter under normal conditions. Then, the first operating power of the reactor is determined according to the first main feed water flow. When 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. Among them, 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. Since the measurement accuracy of the main feed water flow by the flow meter is higher than that of the orifice plate, the uncertainty of the reactor determined based on the main feed water flow measured by the flow meter is lower than the uncertainty of the reactor determined based on the main feed water flow measured by the orifice plate. In this way, by determining the current main feed water flow of the reactor based on the main feed water flow of the reactor measured by the flow meter under normal conditions, the accuracy of obtaining the main feed water flow can be improved, thereby reducing the uncertainty of obtaining the reactor power, and then improving the operating power of the reactor.

[0060] In some embodiments, obtaining a first main feed water flow rate of a reactor by adopting a main feed water flow rate obtaining method corresponding to an operating state includes:

[0061] When the operating state of the flow meter is normal, the first main water supply flow rate is measured by the flow meter.

[0062] Specifically, the operating state of the flow meter may include a normal state and a fault state. When the operating state of the flow meter is a normal state, the first main feed water flow rate of the reactor may be measured by the flow meter.

[0063] In the embodiment of the present application, the flow meter can be a flow meter with higher precision. In one example, the flow meter can be an ultrasonic flow meter. By using the flow meter to measure the first main water supply flow rate, the precision of the main water supply flow rate measurement can be improved.

[0064] In some embodiments, obtaining a first main feed water flow rate of a reactor by adopting a main feed water flow rate obtaining method corresponding to an operating state includes:

[0065] When the running state of the flow meter is a fault state, the second main feed water flow rate of the reactor is measured through the orifice plate;

[0066] The product of the target correction coefficient and the second main feed water flow rate is determined as the first main feed water flow rate; the target correction coefficient is determined based on the main feed water flow rate of the reactor measured by the flow meter under normal conditions.

[0067] Specifically, when the flow meter is in a fault state, the first main feed water flow rate of the reactor can be determined by measuring the second main feed water flow rate of the reactor through the 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 and order of objects.

[0068] In the embodiment of the present application, when the operation state of the flow meter is normal, the main feed water flow rate of the reactor can be measured by the flow meter while the main feed water flow rate of the reactor can be measured by the orifice plate. The ratio of the main feed water flow rate measured by the flow meter to the main feed water flow rate of the reactor measured by the orifice plate is determined as the target correction coefficient.

[0069] In an embodiment of the present application, when correcting the second main feed water flow of the reactor measured by the orifice plate, the temperature of the second main feed water flow collected by the orifice plate can also be corrected, and then the operating power of the reactor is calculated based on the corrected temperature and the corrected main feed water flow, thereby improving the accuracy of the operating power of the reactor.

[0070] In the embodiment of the present application, the second main feed water flow rate of the reactor measured by the orifice plate is corrected, and the first main feed water flow rate can be determined by multiplying the target correction coefficient by the second main feed water flow rate. By determining the target correction coefficient to correct the second main feed water flow rate measured by the orifice plate, the accuracy of the main feed water flow rate can be improved.

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

[0072] When the operation state of the flow meter is normal, obtaining the third main feed water flow rate of the reactor measured by the flow meter and the fourth main feed water flow rate of the reactor measured by the orifice plate;

[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 second main feed water flow rate of the reactor measured by the orifice plate, it is necessary to first determine the target correction coefficient. The target correction coefficient is determined by the main feed water flow rate of the reactor measured by the flow meter in a normal state. When the operating state of the flow meter is normal, the third main feed water flow rate of the reactor measured by the flow meter and the fourth main feed water flow rate of the reactor measured by the orifice plate can be obtained. Among them, the third main feed water flow rate of the reactor measured by the flow meter and the fourth main feed water flow rate of the reactor measured by the orifice plate are measured at the same time.

[0075] In the embodiment of the present application, the ratio of the third main feed water flow rate of the reactor measured by the flow meter to the fourth main feed water flow rate of the reactor measured by the orifice plate can be determined as the target correction coefficient. Furthermore, when the operation state of the flow meter is a fault state, the main feed water flow rate measured by the orifice plate can be multiplied by the target correction coefficient to obtain the corrected main feed water flow rate.

[0076] In the embodiment of the present application, the value of the target correction coefficient changes according to the changes in the main water supply flow rate measured by the flow meter and the main water supply 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 water supply flow measured by the orifice plate can be corrected when the operating state of the flow meter is a fault state, thereby improving the accuracy of the main water supply flow.

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

[0079] When the duration of the flow meter being in a fault state reaches a preset duration, obtaining the fifth main water supply flow collected by the orifice plate;

[0080] determining a third operating power according to a fifth main feedwater flow rate;

[0081] When 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 operating state of the flow meter is a fault state, the first main feed water flow rate of the reactor is determined by the main feed water flow rate measured by the orifice plate and the target correction coefficient, and the first operating power of the reactor is obtained by calculation. After the operating power of the reactor is controlled to increase from the first operating power to the second operating power, when the duration of the flow meter in the fault state reaches a preset duration, the fifth main feed water flow rate collected by the orifice plate is obtained, and the third operating power is determined according to the fifth main feed water flow rate.

[0083] In an embodiment of the present application, when the third operating power is not equal to the second maximum operating power of the reactor, in order to ensure the safe operation of the reactor, it is necessary to adjust the operating power of the reactor from the third operating power to the fourth operating power. When the third operating power is less than the second maximum operating power of the reactor, the operating power of the reactor is increased from the third operating power to the fourth operating power; when the third operating power is greater than the second maximum operating power of the reactor, the operating power of the reactor is reduced from the third operating power to the fourth operating power. Among them, 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 maximum design power of the reactor.

[0084] In the embodiment of the present application, since the accuracy of the main feed water flow collected by the orifice plate is low, when the duration of the flow meter in the fault state reaches the preset duration, the maximum operating power of the reactor can be reduced to ensure the safe operation of the reactor. In one example, the maximum design power of the reactor is 102%. Since the uncertainty of the reactor power measurement is increased 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 operating power of the reactor can be increased from the third operating power to the fourth operating power; when the calculated third operating power is greater than 100%, the operating power of the reactor 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 of 100% of the second maximum operating power.

[0085] In the embodiment of the present application, within a preset time period, when the operating state of the flow meter is converted from a fault state to a normal state, the first main feed water flow of the reactor continues to be collected through the flow meter.

[0086] In this embodiment, when the duration of the flow meter being in a fault state reaches a preset duration, the main feed water flow is collected through the orifice plate, and the operating power is calculated and controlled based on the main feed water flow collected by the orifice plate. Since the accuracy of the main feed water flow collected by the orifice plate is low, when the duration of the flow meter being in a fault state reaches a preset duration, the maximum operating power of the reactor is reduced, thereby ensuring the safe operation of the reactor.

[0087] In some embodiments, determining a first operating power of the reactor according to the first main feedwater flow rate includes:

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

[0089] Determining the thermal power of the steam generator according to the wet steam enthalpy, the feed water enthalpy, the blowdown enthalpy, the blowdown flow rate, and the first main feed water flow rate;

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

[0091] Specifically, when determining the first operating power of the reactor according to 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 first determined according to the temperature of the main feedwater flow rate. Among them, 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 Indicates the thermal power of the steam generator, H v represents the wet steam enthalpy, H e Indicates the feed water enthalpy, Q e Indicates the main water supply flow, H p Indicates the discharge enthalpy, Q p Indicates the sewage flow rate.

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

[0095]

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

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

[0098] See also Figure 2 , is the second flow chart of the power control method of the reactor provided in the embodiment of the present application. Figure 2 As shown, the power control method of the reactor includes the following steps:

[0099] S201, obtaining a flow meter signal.

[0100] S202, flow meter fault judgment, if the flow meter is faulty, go to S203, if the flow meter is normal, go to S206.

[0101] S203, the power output is switched to the reactor power calculation module 2, the correction coefficient is maintained at the value before the fault, and the reactor operates at 101.7% of the full power.

[0102] S204, determine whether it is repaired within x time, if it is repaired, go to S205, if not, go to S206.

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

[0104] S206, the power output is switched to the reactor power calculation module 3, the correction coefficient is calculated, and the reactor operates at 101.7% of full power.

[0105] In this specific embodiment, a nuclear power equipment is taken as a steam generator for example. The specific implementation can refer to the above description, which will not be repeated here.

[0106] See also Figure 3 , is a schematic diagram of a reactor power calculation program provided in an embodiment of the present application. Figure 3 As shown, the reactor power calculation program in the present application includes three reactor power calculation modules. Reactor power calculation module 1 uses the main feed water flow measured by the orifice plate to calculate the reactor power, and reactor power calculation module 3 uses the main feed water flow measured by the installed flow meter to calculate the reactor power. Reactor power calculation module 2 calculates the reactor power by making real-time corrections to the main feed water flow measured by the orifice plate.

[0107] In the embodiment of the present application, when the flow meter is in normal operation, the correction coefficient is determined according to the main water flow measured by the orifice plate and the main water flow measured by the flow meter. The correction coefficient can be expressed as:

[0108]

[0109] Among them, k Q Indicates the correction factor, Q CSB Indicates the main water flow rate measured by the flowmeter, Q KBF Indicates the main feed water flow measured by the orifice plate.

[0110] After the correction coefficient is determined, when the flow meter fails, the product of the correction coefficient and the current main water supply flow measured by the orifice plate can be determined as the corrected main water supply flow.

[0111] In the embodiment of the present application, when the flow meter is in a normal operating state, the nuclear power plant calculates the reactor power with the reactor power calculation module 3 and controls the operation at 101.7% of full power. At the same time, the reactor power calculation module 2 calculates the reactor operating power by making a real-time correction to the main feed water flow measured by the orifice plate, so that the output result is equal to the reactor operating power calculated by the reactor power calculation module 3.

[0112] If the flow meter is in a faulty state, it will enter the fault mode, the correction coefficient of the reactor power calculation module 2 will remain unchanged at the value before the fault, and the nuclear power plant will calculate the reactor power with the reactor power calculation module 2 and continue to control the operation at 101.7% full power for a period of time (recorded as x time). The x time depends on the fault repair time of the flow meter and the drift degree of the orifice plate measurement accuracy during the repair period, which can generally be 2-3 days.

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

[0114] If the flow meter does not return to normal after operating in the fault mode for more than x time, the nuclear power plant switches to calculating the reactor power using the reactor power calculation module 1, and the reactor power is reduced to 100% full power and continues to operate. After the flow meter returns to normal, it switches back to calculating the reactor power using the reactor power calculation module 3, and returns to normal operation, and the reactor power is increased to 101.7% full power.

[0115] See also Figure 4 , is a schematic diagram of reactor power enhancement provided in the embodiment of the present application. Figure 4As shown, in the embodiment of the present application, since the maximum design power of the reactor is the sum of the uncertainty in reactor power measurement and the maximum operating power of the reactor, and the maximum design power of the reactor is a fixed value. Therefore, the maximum operating power of the reactor can be increased by reducing the uncertainty in reactor power measurement. The nuclear power plant assumes that the uncertainty in reactor power measurement is 2%, the operating power is 100% full power, and it is not allowed to exceed 102% of the reactor's maximum design power. After improving the measurement accuracy, assuming that the uncertainty in reactor power measurement is reduced to 0.3%, the operating power can be increased by 1.7% to 101.7% of full power (the application examples below all use this increased power as an assumption), and it is also not allowed to exceed 102% of full power.

[0116] See also Figure 5 , is a schematic diagram of reactor power measurement provided in an embodiment of the present application. Figure 5 As shown, the test instrument system uses the measured inlet feed water pressure, temperature, flow rate, main steam pressure, blowdown flow rate and other parameters of the steam generator secondary circuit side to calculate the enthalpy rise generated by the secondary circuit working fluid passing through the evaporator, thereby obtaining the energy transferred from the reactor primary circuit to the secondary circuit, and then taking into account the energy obtained and lost by the primary circuit through other equipment, the reactor power is calculated based on the energy balance principle. At the same time, the uncertainty of the reactor power measurement also needs to be calculated. According to the energy balance principle of the primary and secondary circuits, the reactor power and the secondary circuit power can be expressed as:

[0117]

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

[0119] According to the energy balance principle, the thermal power of the steam generator is calculated:

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

[0121] Q v =Q e -Q p

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

[0123] Among them, H v represents the wet steam enthalpy, H p Indicates the discharge enthalpy, H e Indicates the feed water enthalpy, Q v represents the wet steam flow rate, Q p represents the sewage flow rate, Q e Indicates the water flow rate.

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

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

[0126] In the embodiment of the present application, the blowdown enthalpy value corresponds to the enthalpy value of saturated water under the SG outlet pressure, and the enthalpy value of the saturated state is calculated by the water meter according to the measured value of the SG outlet pressure. The feed water enthalpy value is calculated by the water meter according to the measured values ​​of the feed water pressure and temperature.

[0127] According to the above thermal balance principle, the reactor power can be calculated:

[0128]

[0129] According to the thermal balance calculation relationship, the reactor measurement uncertainty can be expressed as:

[0130]

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

[0132] See also Figure 6, is a schematic diagram of the structure of a power control device for a reactor provided in an embodiment of the present application, which is applied to a power control device for a reactor, and the power control device includes an orifice plate and a flow meter, both of which can be used to measure the main feed water flow of the reactor, and the main feed water flow is used to determine the operating power of the reactor; wherein the first uncertainty of the operating power determined based on the main feed water flow measured by the flow meter is less than the second uncertainty of the operating power determined based on the main feed water flow measured by the orifice plate; the second aspect of the embodiment of the present application provides a power control device 60 for a reactor, and the power control device 60 includes:

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

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

[0135] A determination module 63, configured to determine a first operating power of the reactor according to the first main feed water flow rate;

[0136] The control module 64 is used to increase the operating power of the reactor from the first operating power to the 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.

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

[0138] See also Figure 7 , is a structural diagram of a reactor power control device provided in an embodiment of the present application. In a third aspect, an embodiment of the present 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 implementations, the embodiments of the present application further provide a machine-readable storage medium, on which instructions are stored, and when the instructions are executed by a processor, the processor implements the above-mentioned reactor power control method.

[0140] In some embodiments, the embodiments of the present application further provide a computer program product, including a computer program, which, when executed by a processor, implements the power control method of the reactor according to the above-mentioned embodiment.

[0141] Those skilled in the art will appreciate that the embodiments of the present application may be provided as methods, systems, or computer program products. Therefore, the present application may adopt the form of a complete hardware embodiment, a complete software embodiment, or an embodiment in combination with software and hardware. Moreover, the present application may adopt the form of a computer program product implemented in one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) that include computer-usable program code.

[0142] The present application is described with reference to the flowcharts and / or block diagrams of the methods, devices (systems), and computer program products according to the embodiments of the present application. It should be understood that each process and / or box in the flowchart and / or block diagram, as well as the combination of the processes and / or boxes in the flowchart and / or block diagram, can be implemented by computer program instructions. These computer program instructions can be provided to a processor of a general-purpose computer, a special-purpose computer, an embedded processor, or other programmable data processing device to generate a machine, so that the instructions executed by the processor of the computer or other programmable data processing device generate instructions for implementing the processes in the flowchart and / or block diagram. Figure 1 A process or multiple processes and / or boxes Figure 1 These computer program instructions can also be stored in a computer-readable memory that can guide a computer or other programmable data processing device to work in a specific way, so that the instructions stored in the computer-readable memory produce a product including an instruction device, which implements the functions specified in the process. Figure 1 A process or multiple processes and / or boxes Figure 1 These computer program instructions can also be loaded onto a computer or other programmable data processing device, so that a series of operation steps are executed on the computer or other programmable device to produce a computer-implemented process, so that the instructions executed on the computer or other programmable device provide for implementing the process in the process. Figure 1 A process or multiple processes and / or boxes Figure 1 A step that specifies a function 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] The memory may include non-permanent memory in a computer-readable medium, random access memory (RAM) and / or non-volatile memory in the form of read-only memory (ROM) or flash RAM. The memory is an example of a computer-readable medium.

[0145] Computer readable media include permanent and non-permanent, removable and non-removable media that can be implemented by any method or technology to store information. Information can be computer readable instructions, data structures, program modules 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 technology, compact disk read-only memory (CD-ROM), digital versatile disk (DVD) or other optical storage, magnetic cassettes, magnetic tape magnetic disk storage or other magnetic storage devices or any other non-transmission media that can be used to store information that can be accessed by a computing device. As defined herein, computer readable media does not include temporary computer readable media (transitory media), such as modulated data signals and carrier waves.

[0146] It should also be noted that the terms "include", "comprises" or any other variations thereof are intended to cover non-exclusive inclusion, so that a process, method, commodity or device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, commodity or device. In the absence of more restrictions, the elements defined by the sentence "comprises a ..." do not exclude the existence of other identical elements in the process, method, commodity or device including the elements.

[0147] The above are only embodiments of the present application and are not intended to limit the present application. For those skilled in the art, the present application may have various changes and variations. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present application should be included within the scope of the claims of the present application.

[0148] In addition, various embodiments of the present invention may be arbitrarily combined, and as long as they do not violate the concept of the present invention, they should also be regarded as the contents disclosed by the present invention.

Claims

1. A method for controlling power of a reactor, characterized in that: A power control device applied to a reactor, the power control device comprising an orifice plate and a flow meter, wherein both the orifice plate and the flow meter can be used to measure the main feed water flow of the reactor, and the main feed water flow is used to determine the operating power of the reactor; wherein a first uncertainty of the operating power determined based on the main feed water flow measured by the flow meter is less than a second uncertainty of the operating power determined based on the main feed water flow measured by the orifice plate; The power control method comprises: Acquiring the operating state of the flow meter; the operating state is a fault state or a normal state; Acquiring a first main feed water flow rate of the reactor by adopting a main feed water flow rate acquisition method corresponding to the operating state; the first main feed water flow rate is determined based on the main feed water flow rate of the reactor measured by the flow meter in the normal state; determining a first operating power of the reactor according to the first main feedwater flow rate; When 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.

2. The power control method according to claim 1, characterized in that: The method of acquiring the first main feed water flow rate of the reactor by adopting the main feed water flow rate acquisition method corresponding to the operating state includes: When the operation state of the flow meter is normal, the first main water supply flow rate is measured by the flow meter.

3. The power control method according to claim 1, characterized in that: The method of acquiring the first main feed water flow rate of the reactor by adopting the main feed water flow rate acquisition method corresponding to the operating state includes: When the running state of the flow meter is a fault state, the second main feed water flow of the reactor is measured by the orifice plate; The product of a target correction coefficient and the second main feed water flow rate is determined as the first main feed water flow rate; the target correction coefficient is determined based on the main feed water flow rate of the reactor measured by the flow meter in the normal state.

4. The power control method according to claim 3, characterized in that: Before determining the product of the target correction coefficient and the second main feedwater flow rate as the first main feedwater flow rate, the power control method further includes: When the operation state of the flow meter is normal, obtaining the third main feed water flow rate of the reactor measured by the flow meter and the fourth main feed water flow rate of the reactor measured by the orifice plate; 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.

5. The power control method according to claim 1, characterized in that: When the operating state of the flow meter is a fault state, after increasing the operating power of the reactor from the first operating power to the second operating power, the power control method further includes: When the duration of the flow meter being in a fault state reaches a preset duration, obtaining a fifth main water supply flow rate collected by the orifice plate; determining a third operating power according to the fifth main feedwater flow rate; When 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 a 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.

6. The power control method according to claim 1, characterized in that: The step of determining the first operating power of the reactor according to the first main feedwater flow rate comprises: Obtaining wet steam enthalpy, feed water enthalpy, blowdown enthalpy, blowdown flow rate and target heat of the steam generator; the target heat is the heat input to the primary coolant from a heat source other than the reactor; determining a thermal power of a steam generator according to the wet steam enthalpy value, the feed water enthalpy value, the blowdown enthalpy value, the blowdown flow rate, and the first main feed water flow rate; The difference between the thermal power and the target heat is determined as the first operating power.

7. A power control device for a reactor, characterized in that: A power control device applied to a reactor, the power control device comprising an orifice plate and a flow meter, wherein both the orifice plate and the flow meter can be used to measure the main feed water flow of the reactor, and the main feed water flow is used to determine the operating power of the reactor; wherein a first uncertainty of the operating power determined based on the main feed water flow measured by the flow meter is less than a second uncertainty of the operating power determined based on the main feed water flow measured by the orifice plate; The power control device comprises: A first acquisition module is used to acquire the operating state of the flow meter; the operating state is a fault state or a normal state; A second acquisition module is used to acquire a first main feed water flow rate of the reactor by adopting a main feed water flow rate acquisition method corresponding to the operating state; the first main feed water flow rate is determined based on the main feed water flow rate of the reactor measured by the flow meter in the normal state; a determination module, configured to determine a first operating power of the reactor according to the first main feedwater flow rate; A control module, used for increasing 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.

8. A power control device for a reactor, characterized in that: include: a memory configured to store instructions; as well as A processor is configured to call the instructions from the memory and implement the method for controlling the reactor operating power according to any one of claims 1 to 6 when executing the instructions.

9. A machine-readable storage medium, characterized in that: The machine-readable storage medium stores instructions for causing a machine to execute the power control method for a reactor according to any one of claims 1 to 6.

10. A computer program product, characterized in that When the instructions in the computer program product are executed by a processor of a power control device of a reactor, the power control device of the reactor executes the power control method of the reactor as claimed in any one of claims 1 to 6.

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