Online monitoring method, device and equipment for output capacity of nuclear power unit and medium

Abstract

The invention provides an on-line monitoring method, device and equipment for the output capacity of a nuclear power unit and a medium. The on-line monitoring method comprises the steps that the generator outlet electric power of the nuclear power unit, the nuclear island thermal power, the opening degree of a regulating valve, the pollution discharge flow of a steam generator and the corresponding current seawater temperature are obtained; a first correction value is generated based on nuclear island thermal power calculation, a second correction value is generated based on regulating valve opening calculation, and a third correction value is generated based on pollution discharge flow calculation; according to the first correction value, the second correction value and the third correction value, the generator outlet electric power is corrected, and generator corrected electric power is generated; generating corresponding generator reference electric power based on the current seawater temperature; and calculating a difference value between the reference electric power of the generator and the corrected electric power of the generator, and outputting an abnormal alarm when the difference value is greater than a preset threshold value. The output capacity of the nuclear power unit can be monitored, and an alarm is given out in time when abnormity is found.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear power unit performance monitoring, and in particular to an online monitoring method, device, equipment and medium for the output capacity of a nuclear power unit. Background Art

[0002] The output capacity of nuclear power units is affected by many factors, including fluctuations in the thermal power of the nuclear island, changes in seawater temperature, and whether main steam is provided to the auxiliary steam system for the plant. At present, the output power of the generator is mainly monitored by a distributed control system (DCS). Due to these objective factors that affect the output of the unit, it is often only when the performance of the equipment deteriorates seriously that the operating personnel can discover the decline in the output capacity of the unit through DCS monitoring. How to enable the operating personnel to discover the abnormal output capacity of the unit earlier through the DCS system and provide the earliest possible time window for equipment fault troubleshooting has become a technical problem that urgently needs to be solved in the nuclear power field. Summary of the invention

[0003] In view of the above-mentioned shortcomings of the prior art, the purpose of the present invention is to provide an online monitoring method, device, equipment and medium for the output capacity of a nuclear power unit, so as to solve the technical problem that the prior art cannot distinguish the reasons for changes in the output capacity of a nuclear power unit.

[0004] To achieve the above-mentioned and other related purposes, the present invention provides an online monitoring method for the output capacity of a nuclear power unit, comprising:

[0005] Obtain the generator export power of the nuclear power unit, the thermal power of the nuclear island, the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, the blowdown flow of the steam generator, and the corresponding current seawater temperature;

[0006] A first correction value is generated based on the thermal power of the nuclear island, a second correction value is generated based on the opening of the regulating valve from the main steam to the auxiliary steam system, and a third correction value is generated based on the blowdown flow of the steam generator;

[0007] According to the first correction value, the second correction value and the third correction value, the generator output electric power is corrected to generate the generator corrected electric power;

[0008] Based on the current seawater temperature, generating a corresponding generator reference electric power according to the fitted polynomial relationship;

[0009] The difference between the generator reference electric power and the generator corrected electric power is calculated, and when the difference is greater than a preset threshold, an abnormal alarm signal is output.

[0010] In one embodiment of the present invention, the step of generating a corresponding generator reference electric power based on the seawater temperature data comprises:

[0011] A fuel cycle in which the secondary circuit thermal system of a nuclear power unit is in a healthy state is selected as the benchmark fuel cycle;

[0012] Acquire multiple sets of seawater temperatures and corresponding generator reference electric powers within a reference fuel cycle;

[0013] Performing fitting processing on the multiple sets of seawater temperatures and corresponding generator reference electric powers to generate a polynomial relationship between the generator reference electric power and the seawater temperature;

[0014] According to the current seawater temperature, the generator reference electric power is calculated by using the multinomial relationship.

[0015] In one embodiment of the present invention, in the step of obtaining the generator outlet electrical power of the nuclear power unit, the nuclear island thermal power, the opening of the regulating valve from the main steam to the plant auxiliary steam system, the sewage flow of the steam generator and the corresponding current seawater temperature, the generator outlet electrical power, the nuclear island thermal power, the opening of the regulating valve from the main steam to the plant auxiliary steam system, the sewage flow of the steam generator and the current seawater temperature are all arithmetic means within a preset statistical period.

[0016] In one embodiment of the present invention, in the steps of calculating and generating the first correction value based on the thermal power of the nuclear island, calculating and generating the second correction value based on the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, and calculating and generating the third correction value based on the blowdown flow of the steam generator, the first correction value ΔP1 satisfies the following formula:

[0017] ΔP1=P 电 ÷W×W 额定

[0018] Among them, P 电 represents the generator export electrical power, W represents the nuclear island thermal power, W 额定 Indicates the rated thermal power of the nuclear island.

[0019] In one embodiment of the present invention, in the steps of calculating and generating a first correction value based on the thermal power of the nuclear island, calculating and generating a second correction value based on the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, and calculating and generating a third correction value based on the blowdown flow of the steam generator, the second correction value ΔP2 satisfies the following formula:

[0020] ΔP2=K÷6%

[0021] Wherein, K represents the opening data of the regulating valve from the main steam to the auxiliary steam system for plant use.

[0022] In one embodiment of the present invention, in the steps of calculating and generating the first correction value based on the thermal power of the nuclear island, calculating and generating the second correction value based on the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, and calculating and generating the third correction value based on the blowdown flow of the steam generator, the third correction value ΔP3 satisfies the following formula:

[0023] ΔP3=1.5×(Qp-Q 设 )÷Q 设

[0024] Among them, Qp represents the blowdown flow of the steam generator during the statistical period, Q 设 Indicates the design flow rate of the steam generator.

[0025] In one embodiment of the present invention, in the step of performing correction processing on the generator output electric power according to the first correction value, the second correction value and the third correction value to generate the generator corrected electric power, the generator corrected electric power P′ 电 The following formula can be satisfied:

[0026] P′ 电 =P 电 +ΔP1+ΔP2+ΔP3

[0027] Among them, P 电 represents the generator output electric power, ΔP1 represents the first correction value, ΔP2 represents the second correction value, and ΔP3 represents the third correction value.

[0028] The present invention also provides a monitoring system for the output capacity of a nuclear power unit, comprising:

[0029] A data acquisition module is used to obtain the generator outlet power of the nuclear power unit, the thermal power of the nuclear island, the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, the blowdown flow of the steam generator, and the corresponding current seawater temperature;

[0030] A calculation module, used to calculate and generate a first correction value based on the thermal power of the nuclear island, calculate and generate a second correction value based on the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, and calculate and generate a third correction value based on the blowdown flow rate;

[0031] a correction module, configured to perform correction processing on the generator outlet electric power according to the first correction value, the second correction value and the third correction value, so as to generate the generator corrected electric power;

[0032] A reference acquisition module, used for generating a corresponding generator reference electric power based on the current seawater temperature;

[0033] The monitoring alarm module is used to calculate the difference between the reference electric power of the generator and the corrected electric power of the generator, and output an abnormal alarm signal when the difference is greater than a preset threshold.

[0034] The present invention further provides an electronic device, comprising:

[0035] one or more processors;

[0036] A storage device is used to store one or more programs. When the one or more programs are executed by the one or more processors, the electronic device implements the online monitoring method of the output capacity of a nuclear power unit as described in any one of the above items.

[0037] The present invention also provides a computer-readable storage medium having a computer program stored thereon. When the computer program is executed by a processor of a computer, the computer is enabled to execute any of the above-mentioned methods for online monitoring the output capacity of a nuclear power unit.

[0038] As described above, the online monitoring method, device, equipment and medium of the output capacity of a nuclear power unit of the present invention have the following beneficial effects: the present invention can track the output capacity of a nuclear power unit online, and when an abnormal output capacity of the unit is found, an alarm is promptly issued to prompt the operating personnel, thereby realizing early warning of the health deterioration or equipment failure of nuclear power equipment by monitoring the changes in the output capacity of the nuclear power unit. BRIEF DESCRIPTION OF THE DRAWINGS

[0039] Figure 1 A schematic flow chart of an online monitoring method for the output capacity of a nuclear power unit provided in an embodiment of the present invention;

[0040] Figure 2 A structural block diagram of a device for monitoring the output capacity of a nuclear power unit provided in an embodiment of the present invention;

[0041] Figure 3 The structure of the computer system shown is suitable for implementing the electronic device of the embodiment of the present invention. DETAILED DESCRIPTION

[0042] The following describes the embodiments of the present invention by specific examples, and those skilled in the art can easily understand other advantages and effects of the present invention from the contents disclosed in this specification. The present invention can also be implemented or applied through other different specific embodiments, and the details in this specification can also be modified or changed in various ways based on different viewpoints and applications without departing from the spirit of the present invention. It should be noted that the following embodiments and features in the embodiments can be combined with each other without conflict.

[0043] It should be noted that the illustrations provided in the following embodiments are only schematic illustrations of the basic concept of the present invention, and thus the drawings only show components related to the present invention rather than being drawn according to the number, shape and size of components in actual implementation. In actual implementation, the type, quantity and proportion of each component may be changed arbitrarily, and the component layout may also be more complicated.

[0044] In the following description, numerous details are discussed to provide a more thorough explanation of the embodiments of the present invention. However, it is obvious to those skilled in the art that the embodiments of the present invention can be implemented without these specific details. In other embodiments, well-known structures and devices are shown in the form of block diagrams rather than in detail to avoid making the embodiments of the present invention difficult to understand.

[0045] First of all, it should be noted that the fuel cycle of a nuclear power plant refers to a series of processes from loading new nuclear fuel into the reactor to unloading it after the nuclear fuel is exhausted, and then processing it for reuse or disposal. After a fuel cycle, the nuclear power unit will usually be overhauled. Each overhaul will eliminate various defects and improve the operating safety and economy of the nuclear power unit through transformation. A standard fuel cycle is about 18 months. During the fuel cycle, if the health of the nuclear power unit deteriorates, such as the condenser cooling pipe is dirty or the system valve internal leakage deteriorates, it will lead to a decrease in the power generation efficiency of the nuclear power unit and a decrease in the unit output capacity. In addition, the output capacity of the nuclear power unit is also affected by changes in a variety of objective normal factors, including fluctuations in the thermal power of the nuclear island, changes in seawater temperature, and whether main steam is provided to the auxiliary steam system for the plant. According to the existing DCS system, operators cannot distinguish whether the decline in unit output is caused by the deterioration of the health status of the equipment or the change of objective normal factors. Only when the health status of the equipment deteriorates to the point where the unit output drops seriously can operators easily find it. In order to identify the deterioration of equipment health earlier, it is necessary to find ways to eliminate the impact of these objective normal factor changes on the unit's output capacity.

[0046] See also Figure 1 The present invention provides an online monitoring method for the output capacity of a nuclear power unit, which may include the following steps:

[0047] Step S100, obtaining the generator outlet power of the nuclear power unit, the thermal power of the nuclear island, the opening of the regulating valve from the main steam to the auxiliary steam system for the plant, the blowdown flow of the steam generator and the corresponding current seawater temperature;

[0048] Step S200, generating a first correction value based on the thermal power of the nuclear island, generating a second correction value based on the opening of the regulating valve from the main steam to the auxiliary steam system for the plant, and generating a third correction value based on the blowdown flow of the steam generator;

[0049] Step S300, performing correction processing on the generator outlet electric power according to the first correction value, the second correction value and the third correction value to generate the generator corrected electric power;

[0050] Step S400: Generate a corresponding generator reference electric power by fitting a polynomial based on the current seawater temperature;

[0051] Step S500: Calculate the difference between the generator reference power and the generator corrected power, and output an abnormal alarm signal when the difference is greater than a preset threshold.

[0052] In one embodiment of the present invention, the output capacity of the nuclear power unit is expressed as the overall power generation capacity of the unit under different dimensions, depending on the boundary conditions of the unit. The boundary conditions of the unit may include the operating mode of the generator set, the thermal power of the nuclear island, the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, and the sewage flow of the steam generator. Among them, for the operating mode of the generator set, the generator set needs to adjust the output power according to the demand of the power grid during the peak regulation period, rather than the full power output. Therefore, there is no need to monitor the output capacity of the unit during the peak regulation period. The online monitoring method provided by the present invention is applicable to the operating mode of the generator set at full power. For the thermal power of the nuclear island, it can correspond to the thermal power control level of the nuclear island at full power. Taking the CPR1000 unit as an example, its rated thermal power W 额定 It can be set to 2905MW. When the actual nuclear island thermal power deviates from 2905MW, corresponding corrections are required. For the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, it refers to the opening of the steam supply regulating valve from the main steam system to the auxiliary steam system for plant use. Nuclear power plants use main steam to heat desalted water to produce auxiliary steam for plant use, and the main steam supply flow rate varies with the demand for auxiliary steam for plant use. Whether the unit provides auxiliary steam for plant use and the main steam flow rate supplied to the auxiliary steam system for plant use will directly affect the output capacity of the unit. In this embodiment, the zero opening of the regulating valve opening is used as the unit operation benchmark according to the fact that no auxiliary steam heat source for plant use is provided. If the unit supplies auxiliary steam heat for plant use, its impact on the output capacity of the unit needs to be considered and corrected accordingly. For the blowdown flow of the steam generator, taking the CPR1000 unit as an example, the design flow rate of the blowdown flow of the steam generator is 70 tons / hour (t / h). If the actual flow rate deviates from 70t / h, corresponding corrections need to be made. When the above boundary conditions deviate, the actual unit output (i.e., the generator export electric power) needs to be corrected. The corrected unit output is the monitored unit output capacity (i.e., the generator corrected electric power).

[0053] In one embodiment of the present invention, when executing step S100, the generator outlet power of the nuclear power unit, the thermal power of the nuclear island, the regulating valve opening of the main steam to the auxiliary steam system for the plant, the blowdown flow of the steam generator and the corresponding current seawater temperature are obtained. Specifically, the operation data of the nuclear power unit is obtained from the DCS system. The operation data is the arithmetic mean value in the preset statistical period, which may specifically include the generator outlet power P 电 , nuclear island thermal power W, regulating valve opening K from main steam to auxiliary steam system for plant use, blowdown flow Qp of steam generator and seawater temperature T corresponding to the current statistical period. In this embodiment, the statistical period can be set to 20 minutes.

[0054] In one embodiment of the present invention, when executing step S200, the first correction value is generated based on the calculation of the thermal power of the nuclear island, the second correction value is generated based on the calculation of the opening of the regulating valve from the main steam to the auxiliary steam system for the plant, and the third correction value is generated based on the calculation of the blowdown flow of the steam generator. Specifically, the first correction value ΔP1 is generated based on the calculation of the thermal power W of the nuclear island. It should be noted that when the nuclear power unit is at full power, the change of the thermal power W of the nuclear island will affect the electric power P of the generator. 电 In this embodiment, the thermal power W of the nuclear island is related to the output power P of the generator. 电 There is a positive proportional relationship between them. The first correction value ΔP1 is defined as the correction of the nuclear island thermal power W to the rated thermal power W 额定 The first correction value ΔP1 can satisfy the following formula:

[0055] ΔP1=P 电 ÷W×W 额定

[0056] Among them, P 电 represents the generator output power, the unit is MW; W represents the nuclear island thermal power, the unit is MW; W 额定 It indicates the rated thermal power of the nuclear island, and its unit is MW.

[0057] In one embodiment of the present invention, the second correction value ΔP2 is calculated based on the opening K of the regulating valve from the main steam to the auxiliary steam system. The opening of the regulating valve from the main steam to the auxiliary steam system is usually less than 30%. Within this range, for every 6% increase in the opening of the regulating valve, the output capacity of the nuclear power unit will be reduced by about 1MW. In this embodiment, the second correction value ΔP2 is defined as the electric power correction value that corrects the opening K of the regulating valve from the main steam to the auxiliary steam system to zero opening. The second correction value ΔP2 can satisfy the following formula:

[0058] ΔP2=K÷6%(MW)

[0059] Among them, K represents the control valve opening data of the main steam to auxiliary steam system. For different nuclear power units, the control valve opening and flow characteristic curve of the main steam to auxiliary steam system are different, and the ΔP2 calculation formula needs to be modified according to the control valve opening-flow characteristic curve.

[0060] In one embodiment of the present invention, the third correction value ΔP3 is calculated based on the steam generator blowdown flow rate Qp. During the full power operation of the nuclear power unit, the change of the blowdown flow rate of the steam generator will affect the output of the unit. The third correction value ΔP3 is defined as the correction of the steam generator blowdown flow rate Qp to the design flow rate Q 设 In this embodiment, according to the statistical data of existing nuclear power plants, the blowdown flow rate of the steam generator is its design flow rate Q 设 When the discharge flow rate is 0t / h, the corresponding unit output capacity will drop by about 1.5MW compared to when the discharge flow rate is 0t / h. Therefore, the third correction value ΔP3 can satisfy the following formula:

[0061] ΔP3=1.5×(Qp-Q 设 )÷Q 设

[0062] Among them, Qp represents the blowdown flow of the steam generator during the statistical period, and its unit is t / h, Q 设 Indicates the design flow rate of the steam generator, the unit is t / h.

[0063] In one embodiment of the present invention, when step S300 is executed, the generator outlet electric power is corrected according to the first correction value, the second correction value and the third correction value to generate the generator corrected electric power. Specifically, according to the first correction value (ΔP1), the second correction value (ΔP2) and the third correction value (ΔP3) calculated in step S200, the generator outlet electric power P is corrected. 电 Correct the nuclear island thermal power W to the rated thermal power W 额定 , the opening K of the regulating valve from the main steam to the auxiliary steam system is corrected to zero opening, and the blowdown flow Qp of the steam generator is corrected to the design flow Q 设 , thus obtaining the corrected generator power P′ 电 In this embodiment, the generator corrected electric power P′ 电 The following formula can be satisfied:

[0064] P′ 电 =P 电 +ΔP1+ΔP2+ΔP3(MW).

[0065] From this, we can know that the generator corrected electric power P' 电The effects of the changes in the nuclear island thermal power W, the regulating valve opening K of the main steam to auxiliary steam system, and the steam generator blowdown flow Qp on the generator outlet power P are eliminated. 电 The impact produced reflects the unit's output capacity under the current seawater temperature, and provides a data basis for subsequent judgment on whether the nuclear power unit's output capacity is normal.

[0066] In one embodiment of the present invention, when executing step S400, that is, based on the seawater temperature data, the corresponding generator reference electric power is generated. Specifically, the following steps may be included:

[0067] Step S410, selecting a fuel cycle in which the secondary circuit thermal system of the nuclear power unit is in a healthy state as a reference fuel cycle;

[0068] Step S420, obtaining multiple sets of seawater temperatures and corresponding generator reference electric powers of the nuclear power unit in the reference fuel cycle;

[0069] Step S430, performing fitting processing on multiple sets of seawater temperatures and corresponding generator reference electric powers to generate a polynomial relationship between the generator reference electric power and the seawater temperature;

[0070] Step S440: Based on the current seawater temperature, a generator reference electric power corresponding to the current seawater temperature is generated by fitting a polynomial relationship.

[0071] In one embodiment of the present invention, when step S410 is executed, a fuel cycle in which the secondary circuit thermal system of the nuclear power unit is in a healthy state is selected as the reference fuel cycle. Specifically, the first fuel cycle of the nuclear power unit can usually be selected as the reference fuel cycle, or other fuel cycles with better health status of the unit can be selected as the reference fuel cycle according to actual conditions. The seawater temperature range during the full-power operation of the unit in the reference fuel cycle should be large enough to basically cover the local seawater temperature range from the lowest to the highest. The reference fuel cycle requires that the main equipment of the secondary circuit thermal system such as turbines, condensers, heaters, steam-water separation reheaters, important pumps, etc. are in a healthy state, and the system has no obvious internal or external leakage.

[0072] In one embodiment of the present invention, when step S420 is executed, multiple sets of seawater temperatures and corresponding generator reference electric powers of the nuclear power unit in the reference fuel cycle are obtained. Specifically, first, the generator corrected electric power in the reference fuel cycle is defined as the generator reference electric power. Then, at least 30 sets of seawater temperatures and corresponding generator reference electric powers when the unit is running stably at full power in the reference fuel cycle are obtained, and the obtained seawater temperature should basically cover the local lowest to highest seawater temperature range. In this embodiment, the nuclear island thermal power, the regulating valve opening of the main steam to the auxiliary steam system for plant use, the steam generator blowdown flow, the generator outlet electric power, and the seawater temperature for 20 consecutive minutes of stable operation of the unit at full power every day during the unit's reference fuel cycle are obtained from the DCS system, and the arithmetic mean of these parameters is obtained as the first set of thermal parameters. Based on the first set of thermal parameters, and with reference to the process of steps S100 to S300, a set of generator reference electric power data corresponding to the seawater temperature can be calculated.

[0073] In one embodiment of the present invention, when step S430 is executed, multiple sets of seawater temperatures and corresponding generator reference electric powers are fitted to generate a polynomial relationship between the generator reference electric power and the seawater temperature. Specifically, first, in software such as EXCEL, multiple sets of seawater temperatures and corresponding generator reference electric powers in the reference fuel cycle are plotted into a scatter plot. Then, the scatter plot is fitted to obtain a relationship curve between the generator reference electric power and the seawater temperature. In this embodiment, the above relationship curve can be described by a quadratic polynomial relationship or a higher-order polynomial relationship.

[0074] In one embodiment of the present invention, when step S440 is executed, the generator reference electric power corresponding to the current seawater temperature is generated through a polynomial relationship. Specifically, the generator reference electric power at different seawater temperatures can be obtained according to the polynomial relationship fitted in step S430. In this embodiment, the current seawater temperature is substituted into the polynomial relationship to obtain the corresponding generator reference electric power.

[0075] In one embodiment of the present invention, when step S500 is executed, the difference between the generator reference electric power and the generator corrected electric power is calculated, and when the difference is greater than a preset threshold, an abnormal alarm signal is output. Specifically, due to the uncertainty in the measurement of thermal parameters, the calculated generator corrected electric power and generator reference electric power also have uncertainty. When the difference between the generator reference electric power and the generator corrected electric power is small, it may be caused by measurement uncertainty. Only when the difference reaches a certain threshold value does it mean that the unit output capacity may be abnormal, and it is necessary to issue an abnormal alarm to the operating personnel for prompting. In this embodiment, the difference threshold between the generator reference electric power and the generator corrected electric power can be set to 3MW. When the difference between the two is less than or equal to the difference threshold, it is judged that the current unit output capacity is normal; when the difference between the two is greater than the difference threshold, it is judged that the current unit output capacity is abnormal. After receiving the alarm, the operating personnel notify the relevant professionals to investigate the reasons for the decline in the unit output capacity.

[0076] Furthermore, the corrected electric power of the generator can be tracked online in the DCS system. In this embodiment, the corrected electric power of the generator can be recorded in the DCS system according to a preset period, and the corrected electric power of the generator can be compared and displayed with the corresponding generator reference electric power. Specifically, two data displays are added in the DCS system, one of which is the current corrected electric power of the nuclear power unit, and the other is the reference electric power of the generator corresponding to the current seawater temperature. In this embodiment, the preset period can be set to record every 5 minutes. According to steps S100 to S500, the generator export electric power, nuclear island thermal power, main steam to auxiliary steam system regulating valve opening, steam generator sewage flow, and seawater temperature are obtained in sequence from the current time period (for example, 20 minutes) to the previous statistical time period, and the corrected electric power of the generator and the corresponding reference electric power of the generator are calculated in the DCS system, and then the data is displayed, and the trend curve of the corrected electric power of the generator and the reference electric power of the generator over time is displayed. The display time period range can be customized.

[0077] See also Figure 2 The present invention also provides a monitoring device for the output capacity of a nuclear power unit, which may include a data acquisition module 100, a calculation module 200, a correction module 300, a reference acquisition module 400 and a monitoring alarm module 500. Each functional module is described in detail as follows.

[0078] In one embodiment of the present invention, the data acquisition module 100 can be used to obtain the generator outlet power of the nuclear power unit, the thermal power of the nuclear island, the regulating valve opening of the main steam to the auxiliary steam system for the plant, the blowdown flow of the steam generator, and the seawater temperature. Further, the data acquisition module 100 can be specifically used to obtain the operating data of the nuclear power unit from the DCS system. The operating data is the arithmetic mean value within a preset time period, which can specifically include the generator outlet power P电 , nuclear island thermal power W, regulating valve opening K from main steam to auxiliary steam system for plant use, blowdown flow Qp of steam generator, seawater temperature T. In this embodiment, the statistical period can be set to 20 minutes, during which the seawater temperature needs to remain stable, and its change value should be less than 0.1°C.

[0079] In one embodiment of the present invention, the calculation module 200 can be used to generate a first correction value based on the nuclear island thermal power calculation, generate a second correction value based on the main steam to auxiliary steam system control valve opening calculation, and generate a third correction value based on the steam generator blowdown flow calculation. Further, the calculation module 200 can be specifically used to first calculate and generate a first correction value (ΔP1) based on the nuclear island thermal power W. During the full power period of the unit, the nuclear island thermal power W and the generator outlet power P 电 There is a positive proportional relationship between them. The first correction value is defined as the correction of the nuclear island thermal power W to the rated thermal power W 额定 The first correction value can satisfy the following formula:

[0080] Δp1=p 电 ÷W×W 额定

[0081] Among them, P 电 represents the generator output power, the unit is MW; W represents the nuclear island thermal power, the unit is MW; W 额定 It indicates the rated thermal power of the nuclear island, and its unit is MW.

[0082] Then, the second correction value (ΔP2) is calculated based on the opening K of the regulating valve from the main steam to the auxiliary steam system for the plant. In this embodiment, the second correction value is defined as the electric power correction value for correcting the opening K of the regulating valve from the main steam to the auxiliary steam system for the plant to zero opening. The second correction value can satisfy the following formula:

[0083] ΔP2=K÷6%(MW)

[0084] Among them, K represents the opening of the regulating valve from the main steam to the auxiliary steam system used in the plant.

[0085] Finally, the third correction value (ΔP3) is calculated based on the steam generator blowdown flow rate Qp. In this embodiment, according to the existing nuclear power plant statistical data, the steam generator blowdown flow rate is its design flow rate Q 设 When the steam generator blowdown flow is 0t / h, the corresponding unit output capacity will decrease by about 1.5MW. Therefore, the third correction value can satisfy the following formula:

[0086] ΔP3=1.5×(Qp-Q 设 )÷Q 设 (MW)

[0087] Where Qp represents the blowdown flow of the steam generator during the statistical period, and its unit is t / h; Q 设 Indicates the design flow rate of the steam generator, the unit is t / h.

[0088] In one embodiment of the present invention, the correction module 300 can be used to correct the generator export electric power according to the first correction value, the second correction value and the third correction value to generate the generator corrected electric power. Further, the correction module 300 can be specifically used to correct the generator export electric power P according to the first correction value (ΔP1), the second correction value (ΔP2) and the third correction value (ΔP3) calculated in step S200. 电 Correct the nuclear island thermal power W to the rated thermal power W 额定 , the regulating valve opening K is corrected to zero opening, and the steam generator blowdown flow Qp is corrected to the design flow Q 设 , thus obtaining the corrected generator power P′ 电 In this embodiment, the generator corrected electric power P′ 电 The following formula can be satisfied:

[0089] P′ 电 =P 电 +ΔP1+ΔP2+ΔP3(MW).

[0090] In one embodiment of the present invention, the benchmark acquisition module 400 can be used to generate a corresponding generator benchmark electric power based on the current seawater temperature. Further, the benchmark acquisition module 400 can be specifically used to obtain multiple sets of seawater temperatures and corresponding generator benchmark electric powers in the benchmark fuel cycle of the nuclear power unit; perform fitting processing on the multiple sets of seawater temperatures and corresponding generator benchmark electric powers to generate a polynomial relationship between the generator benchmark electric power and the seawater temperature; and generate the generator benchmark electric power corresponding to the current seawater temperature according to the polynomial relationship.

[0091] In one embodiment of the present invention, the monitoring alarm module 500 can be used to calculate the difference between the generator reference power and the generator corrected power, and output an abnormal alarm when the difference is greater than a preset threshold. Further, the monitoring alarm module 500 can be specifically used to calculate the difference between the generator reference power and the generator corrected power, and determine whether there is an abnormality in the nuclear power unit according to the size of the difference, and issue an abnormal alarm to the operating personnel to prompt when an abnormality occurs. In this embodiment, the difference threshold between the generator reference power and the generator corrected power can be set to 3MW. When the difference between the two is less than or equal to the difference threshold, it is judged that the nuclear power unit is operating normally; when the difference between the two is greater than the difference threshold, it is judged that the nuclear power unit is operating abnormally, and the operating personnel should be prompted to investigate the cause of the decline in the unit's output capacity.

[0092] The specific definition of the monitoring device for the output capacity of nuclear power units can be found in the above-mentioned definition of the online monitoring method, which will not be repeated here. Each module in the above-mentioned monitoring device can be implemented in whole or in part by software, hardware and a combination thereof. The above-mentioned modules can be embedded in or independent of the processor in the computer device in the form of hardware, or can be stored in the memory of the computer device in the form of software, so that the processor can call and execute the operations corresponding to the above modules.

[0093] An embodiment of the present invention also provides an electronic device, comprising: one or more processors; a storage device for storing one or more programs, wherein when the one or more programs are executed by one or more processors, the electronic device implements the online monitoring method of the output capacity of a nuclear power unit provided in each of the above embodiments.

[0094] See also Figure 3 It should be noted that Figure 3 The computer system 200 of the electronic device shown is only an example and should not bring any limitation to the functions and scope of use of the embodiments of the present invention.

[0095] See also Figure 3 The computer system 200 includes a central processing unit (CPU) 201, which can perform various appropriate actions and processes according to the program stored in the read-only memory (ROM) 202 or the program loaded from the storage part 208 to the random access memory (RAM) 203, such as executing the method in the above embodiment. In the RAM 203, various programs and data required for system operation are also stored. The CPU 201, the ROM 202 and the RAM 203 are connected to each other through the bus 204. The input / output (I / O) interface 205 is also connected to the bus 204.

[0096] The following components are connected to the I / O interface 205: an input section 206 including a keyboard, a mouse, etc.; an output section 207 including a cathode ray tube (CRT), an organic light emitting diode (OLED), a liquid crystal display (LCD), etc., and a speaker; a storage section 208 including a hard disk, etc.; and a communication section 209 including a network interface card such as a LAN (Local Area Network) card, a modem, etc. The communication section 209 performs communication processing via a network such as the Internet. A drive 210 is also connected to the I / O interface 205 as needed. A removable medium 211, such as a magnetic disk, an optical disk, a magneto-optical disk, a semiconductor memory, etc., is installed on the drive 210 as needed so that a computer program read therefrom is installed into the storage section 208 as needed.

[0097] In particular, according to an embodiment of the present invention, the process described above with reference to the flowchart can be implemented as a computer software program. For example, an embodiment of the present invention includes a computer program product, which includes a computer program carried on a computer readable medium, and the computer program includes a computer program for executing the method shown in the flowchart. In such an embodiment, the computer program can be downloaded and installed from the network through the communication part 209, and / or installed from the removable medium 211. When the computer program is executed by the central processing unit (CPU) 1001, various functions defined in the system of the present invention are executed.

[0098] It should be noted that the computer-readable medium shown in the embodiment of the present invention may be a computer-readable signal medium or a computer-readable storage medium or any combination of the above two. The computer-readable storage medium may be, for example, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, device or device, or any combination of the above. More specific examples of computer-readable storage media may include, but are not limited to: an electrical connection with one or more wires, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM), a flash memory, an optical fiber, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the above. In the present invention, a computer-readable signal medium may include a data signal propagated in a baseband or as part of a carrier wave, which carries a computer-readable computer program. This propagated data signal may take a variety of forms, including but not limited to an electromagnetic signal, an optical signal, or any suitable combination of the above. A computer-readable signal medium may also be any computer-readable medium other than a computer-readable storage medium, which may send, propagate or transmit a program for use by or in conjunction with an instruction execution system, apparatus or device. A computer program contained on a computer-readable medium may be transmitted using any appropriate medium, including but not limited to: wireless, wired, etc., or any suitable combination of the above.

[0099] The flowcharts and block diagrams in the accompanying drawings illustrate the possible architecture, functions and operations of the systems, methods and computer program products according to various embodiments of the present invention. Among them, each box in the flowchart or block diagram can represent a module, a program segment, or a part of the code, and the above-mentioned module, program segment, or a part of the code contains one or more executable instructions for implementing the specified logical function. It should also be noted that in some alternative implementations, the functions marked in the box can also occur in a different order from the order marked in the accompanying drawings. For example, two boxes represented in succession can actually be executed substantially in parallel, and they can sometimes be executed in the opposite order, depending on the functions involved. It should also be noted that each box in the block diagram or flowchart, and the combination of boxes in the block diagram or flowchart, can be implemented with a dedicated hardware-based system that performs a specified function or operation, or can be implemented with a combination of dedicated hardware and computer instructions.

[0100] The units involved in the embodiments of the present invention may be implemented by software or hardware, and the units described may also be arranged in a processor. The names of these units do not, in some cases, limit the units themselves.

[0101] Another aspect of the present invention provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor of a computer, causes the computer to execute the above-mentioned online monitoring method for the output capacity of a nuclear power unit. The computer-readable storage medium may be included in the electronic device described in the above embodiment, or may exist independently without being assembled into the electronic device.

[0102] Another aspect of the present invention further provides a computer program product or a computer program, the computer program product or the computer program includes computer instructions, the computer instructions are stored in a computer-readable storage medium. The processor of the computer device reads the computer instructions from the computer-readable storage medium, and the processor executes the computer instructions, so that the computer device executes the online monitoring method of the output capacity of the nuclear power unit provided in each of the above embodiments.

[0103] In summary, the present invention provides an online monitoring method, device, equipment and medium for the output capacity of a nuclear power unit, which can track the output capacity of a nuclear power unit online, and when an abnormal output capacity of the unit is found, an alarm is promptly issued to prompt the operating personnel, thereby realizing abnormal changes in the output capacity of the nuclear power unit by monitoring the abnormal changes, which is conducive to earlier detection of equipment failures.

[0104] The above embodiments are merely illustrative of the principles and effects of the present invention, and are not intended to limit the present invention. Anyone familiar with the art may modify or alter the above embodiments without departing from the spirit and scope of the present invention. Therefore, all equivalent modifications or alterations made by a person of ordinary skill in the art without departing from the spirit and technical concept disclosed by the present invention shall still be covered by the claims of the present invention.

Claims

1. An online monitoring method for the output capacity of a nuclear power unit, characterized in that: include: Obtain the generator export power of the nuclear power unit, the thermal power of the nuclear island, the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, the blowdown flow of the steam generator, and the corresponding current seawater temperature; A first correction value is generated based on the thermal power of the nuclear island, a second correction value is generated based on the opening of the regulating valve from the main steam to the auxiliary steam system for the plant, and a third correction value is generated based on the sewage flow rate; According to the first correction value, the second correction value and the third correction value, the generator output electric power is corrected to generate the generator corrected electric power; Based on the current seawater temperature, generating a corresponding generator reference electric power; The difference between the generator reference electric power and the generator corrected electric power is calculated, and when the difference is greater than a preset threshold, an abnormal alarm is output.

2. The method for online monitoring of the output capacity of a nuclear power unit according to claim 1, characterized in that: The step of generating a corresponding generator reference electric power based on the seawater temperature data comprises: A fuel cycle in which the secondary circuit thermal system of a nuclear power unit is in a healthy state is selected as the benchmark fuel cycle; Acquire multiple sets of seawater temperatures and corresponding generator reference electric powers within a reference fuel cycle; Performing fitting processing on the multiple sets of seawater temperatures and corresponding generator reference electric powers to generate a polynomial relationship between the generator reference electric power and the seawater temperature; According to the current seawater temperature, the corresponding generator reference electric power is calculated by using the polynomial relationship.

3. The method for online monitoring of the output capacity of a nuclear power unit according to claim 1, characterized in that: In the step of obtaining the generator outlet electrical power of the nuclear power unit, the nuclear island thermal power, the opening of the regulating valve from the main steam to the plant auxiliary steam system, the sewage flow of the steam generator and the corresponding current seawater temperature, the generator outlet electrical power, the nuclear island thermal power, the opening of the regulating valve from the main steam to the plant auxiliary steam system, the sewage flow of the steam generator and the current seawater temperature are all arithmetic means within a preset statistical period.

4. The method for online monitoring of the output capacity of a nuclear power unit according to claim 1, characterized in that: In the steps of calculating and generating a first correction value based on the thermal power of the nuclear island, calculating and generating a second correction value based on the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, and calculating and generating a third correction value based on the blowdown flow rate, the first correction value ΔP1 satisfies the following formula: ΔP1=P 电 ÷W×W 额定 Among them, P 电 represents the generator export electrical power, W represents the nuclear island thermal power, W 额定 Indicates the rated thermal power of the nuclear island.

5. The method for online monitoring of the output capacity of a nuclear power unit according to claim 1, characterized in that: In the steps of generating a first correction value based on the nuclear island thermal power, generating a second correction value based on the regulating valve opening of the main steam to auxiliary steam system, and generating a third correction value based on the blowdown flow rate, the second correction value ΔP2 satisfies the following formula: ΔP2=K÷6% Wherein, K represents the opening degree of the regulating valve from the main steam to the auxiliary steam system for plant use.

6. The method for online monitoring of the output capacity of a nuclear power unit according to claim 1, characterized in that: In the steps of generating a first correction value based on the nuclear island thermal power, generating a second correction value based on the regulating valve opening of the main steam to auxiliary steam system, and generating a third correction value based on the sewage flow rate, the third correction value ΔP3 satisfies the following formula: ΔP3=1.5×(Qp-Q 设 )÷Q 设 Among them, Qp represents the blowdown flow of the steam generator during the statistical period, Q 设 Indicates the designed blowdown flow of the steam generator.

7. The method for online monitoring of the output capacity of a nuclear power unit according to claim 1, characterized in that: In the step of performing correction processing on the generator output electric power according to the first correction value, the second correction value and the third correction value to generate the generator corrected electric power, the generator corrected electric power P ′ 电 The following formula can be satisfied: P ′ 电 =P 电 +ΔP1+ΔP2+ΔP3 Among them, P 电 represents the generator export electric power, ΔP1 represents the first correction value, ΔP2 represents the second correction value, and ΔP3 represents the third correction value.

8. A monitoring system for the output capacity of a nuclear power unit, characterized in that: include: A data acquisition module is used to obtain the generator outlet power of the nuclear power unit, the thermal power of the nuclear island, the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, the blowdown flow of the steam generator, and the corresponding current seawater temperature; A calculation module, used to calculate and generate a first correction value based on the thermal power of the nuclear island, calculate and generate a second correction value based on the opening of the regulating valve from the main steam to the auxiliary steam system for plant use, and calculate and generate a third correction value based on the blowdown flow rate; a correction module, configured to perform correction processing on the generator outlet electric power according to the first correction value, the second correction value and the third correction value, so as to generate the generator corrected electric power; A reference acquisition module, used for generating a corresponding generator reference electric power based on the current seawater temperature; The monitoring alarm module is used to calculate the difference between the reference electric power of the generator and the corrected electric power of the generator, and output an abnormal alarm signal when the difference is greater than a preset threshold.

9. An electronic device, characterized in that: The electronic device comprises: one or more processors; A storage device for storing one or more programs, which, when executed by the one or more processors, enables the electronic device to implement the online monitoring method for the output capacity of a nuclear power unit as described in any one of claims 1 to 7.

10. A computer-readable storage medium, characterized in that: A computer program is stored thereon, and when the computer program is executed by a processor of a computer, the computer is caused to execute the online monitoring method for the output capacity of a nuclear power unit as claimed in any one of claims 1 to 7.

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