Method for correcting input signals of a nuclear power plant reactor power control system

Abstract

The present application belongs to the technical field of nuclear power plant instrument control system, and particularly relates to a nuclear power plant reactor power control system input signal correction method. S and N core from the reactor core measurement system; S2, the real-time reactor core neutron fluence rate signal N core and the nuclear power measurement signal N S are compared in an adder to obtain a power deviation initial signal N E1 ; S3, the power deviation initial signal N E1 enters a power deviation logic processor for logic processing and outputs N E2 ; S4, a correction mode is selected in a nuclear power correction selector according to an operation condition and a procedure, and a nuclear power correction signal N E is output; S5, the nuclear power measurement value signal N S and the nuclear power correction signal N E are operated in an adder to obtain a control nuclear power signal N C . The present application can more accurately reflect the real situation of the reactor core power; the corrected nuclear power signal is used for the reactor power control system, and the safety and economy of the power plant operation are improved.

Description

Technical Field

[0001] This invention belongs to the technical field of nuclear power plant instrumentation and control systems, and specifically relates to a method for correcting input signals of a nuclear power plant reactor power control system. Background Technology

[0002] Among existing technologies, there are several domestic studies on key parameters of self-supplied neutron detectors (SPNDs) for reactor core neutron flux measurement systems. These studies analyze the key nuclear and electrical performance parameters of the SPNDs used in the Hualong One reactor core neutron flux measurement system, and provide a design scheme for the SPNDs. There are also analyses of practical application problems in reactor core neutron flux measurement systems. These analyses address issues such as detector jamming and channel unavailability, examining the relationship between the detector and its drive and selection equipment, and deriving solutions to the defects in the detector and related equipment. Furthermore, there are publicly reported studies on nuclear instrumentation systems for nuclear power plant cores, which utilize differential neutron self-supplied detectors to measure the three-dimensional neutron flux of the reactor core in real time. These studies also utilize digital processing and display equipment to give the system strong computational and graphical display capabilities, enabling real-time processing of measured data and online generation of three-dimensional power distribution maps of the reactor core.

[0003] Domestic research analyzes practical application problems of reactor core neutron flux rate measurement systems. This literature considers the crucial role of core neutron flux rate in studying the distribution and magnitude of core axial power and calibrating various core data. To ensure the reliability of neutron flux rate measurement equipment, it proposes solutions addressing defects in neutron flux rate detectors and related equipment. Specifically, this literature focuses on improving the reliability of the core neutron flux rate measurement system by addressing the inherent defects of the detectors and related processing equipment, thus improving the usability of the neutron flux rate signal to a certain extent. Another literature proposes a nuclear instrumentation system for nuclear power plant cores. This system can measure the three-dimensional neutron flux rate of the core online in real time, process the measured data in real time, and generate a three-dimensional power distribution map of the core online. This literature achieves real-time measurement and processing of the three-dimensional neutron flux rate of the core by employing new measurement methods and digital processing and display equipment. However, none of the above literature mentions the use of neutron flux rate signals for correcting the nuclear power signals of the reactor power control system. The neutron flux signal from the core measurement system more accurately reflects the true core power. Therefore, this signal is used to correct the nuclear power signal, thus providing a more accurate reflection of the true core power. However, due to the inherent time delay in the in-core signal, the compensation power is accurate only when the core power is relatively stable. If power fluctuations are significant, the correction power cannot accurately reflect the immediate fluctuations, exhibiting a lag. Therefore, the decision to correct the nuclear power signal, and the appropriate method for doing so, should be based on the actual operating conditions of the power plant.

[0004] The reactor power control system is a crucial safety control system in nuclear power plants, and its performance directly affects the safe and economical operation of the plant. The basic function of the reactor power control system is to regulate the reactor power to match the turbine load; therefore, the nuclear power signal is a vital input signal in the reactor power control system. Summary of the Invention

[0005] The technical problem solved by this invention is to propose a method for correcting the input signal of a nuclear power plant reactor power control system. By introducing the core neutron flux signal from the core measurement system, the nuclear power signal of the nuclear instrumentation system is corrected, thereby more accurately reflecting the true state of the core power. The corrected nuclear power signal is used in the reactor power control system, improving the safety and economy of the power plant operation.

[0006] The technical solution adopted in this invention is as follows:

[0007] A method for correcting the input signal of a nuclear power plant reactor power control system specifically includes the following steps:

[0008] S1, The reactor power control system acquires nuclear power measurement signals from the nuclear instrumentation system. S and the real-time core neutron flux rate signal N from the core measurement system core ;

[0009] S2, the real-time core neutron flux rate signal N core and nuclear power measurement signal N S The comparison is performed in the adder to obtain the initial power deviation signal N. E1 ;

[0010] S3, the initial power deviation signal N E1 The power deviation logic processor processes the input and outputs N. E2 ;

[0011] S4. Select the correction method in the nuclear power correction selector according to the operating conditions and procedures, and output N. E ;

[0012] S5, Nuclear power measurement signal N S and nuclear power correction signal N E The operation is performed in the adder to obtain the control nuclear power signal N. C .

[0013] The initial signal N of the power deviation E1 N E1 =N core -N S .

[0014] The dead zone value E = 2%FP.

[0015] The initial signal N of the power deviation E1 The power deviation logic processor then performs logic processing, which includes the following steps:

[0016] The aforementioned power deviation initial signal N E1 After passing through the dead-time function F(x), which sets the dead-time value to E, the power deviation signal N... E1 When the absolute value is greater than E, it enters the proportional coefficient K stage for calculation and then outputs N. E2 Otherwise, the output will be 0.

[0017] The nuclear power measurement value N S Entering the power deviation logic processor, K takes different values ​​depending on whether the nuclear power plant is in the high or low power range, N S When FP > 30%, K = 0; N S When ≤30%FP, K=1.05.

[0018] The N E2 =K·N E1 .

[0019] The step of selecting the correction method in the nuclear power correction selector based on operating conditions and procedures includes the following steps:

[0020] To determine if the core power is stable, if the core power is unstable, the F-type reactor is selected through a nuclear power correction method. mode The nuclear power correction selector is controlled to select no correction; the nuclear power correction selector outputs N. E =0;

[0021] When the core power is stable, the input signal to the nuclear power plant's reactor power control system is corrected.

[0022] Correcting the input signals of the nuclear power plant reactor power control system includes two modes:

[0023] When automatic correction mode is selected, the nuclear power correction selector outputs N. E =N E2 ;

[0024] When manual correction mode is selected, the nuclear power correction selector outputs N. E =N E3 .

[0025] The N E3 The method for determining it is as follows: based on the nuclear power measurement value N from the nuclear instrumentation system. S Real-time core neutron flux rate signal N from the core measurement system core And the actual operating status of the power plant, by manually inputting the correction value N.E3 .

[0026] Compared with the prior art, the beneficial effects of the present invention are as follows:

[0027] (1) The present invention provides a method for correcting the input signal of a nuclear power plant reactor power control system. The method uses the core neutron flux rate signal to correct the important input signal of the reactor power control system, the nuclear power signal, so as to more accurately reflect the true situation of the core power.

[0028] (2) The present invention provides a method for correcting the input signal of a nuclear power plant reactor power control system, which can more accurately reflect the true situation of the reactor core power. The corrected nuclear power signal is used in the reactor power control system, which improves the safety and economy of the power plant operation. Attached Figure Description

[0029] Figure 1 Flowchart of the method for correcting input signals to the reactor power control system;

[0030] Figure 2 A block diagram illustrating the principle of a method for correcting input signals to a reactor power control system;

[0031] Figure 3 This is the schematic diagram of the power deviation logic processor;

[0032] In the figure: 1: Real-time core neutron fluence signal N core 2: Nuclear power measurement signal N S 3: Adder; 4: Power deviation logic processor; 5: Dead-time function F(x); 6: Proportional coefficient K; 7: Initial signal N for power deviation E1 8: Manual correction value N E3 9: Automatic power deviation correction signal N E2 10: Nuclear power correction selector; 11: Nuclear power correction mode F mode 12: Nuclear power correction signal N E 13: Control nuclear power signal N C . Detailed Implementation

[0033] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0034] In the description of this invention, it should be noted that the terms "center," "upper," "lower," "left," "right," "vertical," "horizontal," "inner," and "outer," etc., indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are used only for the convenience of describing the invention and for simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on the invention. Furthermore, the terms "first," "second," and "third" are used for descriptive purposes only and should not be construed as indicating or implying relative importance.

[0035] In the description of this invention, it should be noted that, unless otherwise explicitly specified and limited, the terms "installation," "connection," and "linking" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral connection; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; and they can refer to the internal connection of two components. Those skilled in the art can understand the specific meaning of the above terms in this invention based on the specific circumstances.

[0036] This invention considers that the neutron flux rate signal in the reactor core more accurately reflects the true state of the core power, and therefore utilizes this signal to correct the nuclear power signal. However, due to the inherent time delay in the in-core signal, the compensation power is accurate only when the core power is relatively stable, making the nuclear power signal correction effective under these power plant operating conditions. Once power fluctuations are significant, the correction power cannot accurately reflect the immediate fluctuations, exhibiting a lag; therefore, it is not advisable to correct the nuclear power signal under these power plant operating conditions. Thus, the decision to correct the nuclear power signal, and the appropriate method of correction, should be based on the actual operating conditions of the power plant, i.e., whether the reactor core power is stable.

[0037] like Figure 1 and Figure 2 As shown, the present invention provides a method for correcting the input signal of a nuclear power plant reactor power control system, which specifically includes the following steps:

[0038] Step 1: The reactor power control system acquires nuclear power measurement signals N from the nuclear instrumentation system. S 2 and the real-time core neutron flux rate signal N from the core measurement system. core 1.

[0039] Step 2, the real-time core neutron flux rate signal N core 1 and nuclear power measurement signal N S 2. The comparison is performed in adder 3 to obtain the initial power deviation signal N. E1 7, N E1 =N core -NS ;

[0040] Step 3, the initial power deviation signal N E1 7. The logic is processed by the power deviation logic processor 4.

[0041] The schematic diagram of the power deviation logic processor 4 is as follows: Figure 2 As shown, the initial signal N of the power deviation E1 7. First, it needs to pass through the dead-zone function F(x), which sets the dead-zone value to E. When -E ≤ N E1 When N ≤ E, f(x) = 0; when N ≤ E, f(x) = 0. E1 <-E or N E1 When >E, f(x) = N E1 The purpose of setting this dead-time function is to ensure that the real-time core neutron fluence signal N... core 1 and nuclear power measurement value N S Power correction is only performed when the deviation between the two reaches a certain limit. This certain limit is defined as follows: dead zone function dead zone E = 2%FP (FP: full power). When the power deviation signal N... E1 Only when the absolute value is greater than 2%FP will the operation proceed to the scaling factor K6 stage; otherwise, the output will be 0.

[0042] Meanwhile, the nuclear power measurement value N S The signal enters the power deviation logic processor, which determines the value of the proportional coefficient K. The initial power deviation signal N... E1 7. When performing proportional calculations in the proportional coefficient K6 stage, different proportional coefficients are used for the initial power deviation signal N, depending on whether the nuclear power plant is operating at high or low power. E1 Process again, N E2 =K·N E1 Where K takes different values ​​depending on whether the nuclear power plant is in the high or low power range, N S When FP > 30%, K = 0; N S When ≤30%FP, K=1.05.

[0043] According to the nuclear power measurement signal N S The magnitude of the power deviation is used to determine the operating condition of the nuclear power plant. If the threshold between high and low power is set at 30% FP, and the proportional coefficient K is 0 at high power and 1.05 at low power, then this means the nuclear power plant does not automatically correct the power signal when the power deviation is greater than 30% FP, but automatically corrects the power signal when the power deviation is less than or equal to 30% FP. The automatically corrected value is N, the value of the initial power deviation signal processed by the proportional coefficient K. E2 .

[0044] Step 4: When the nuclear power plant is running, select the correction method in the nuclear power correction selector 10 according to the operating conditions and procedures.

[0045] To determine if the core power is stable, if the core power is unstable, the F-type reactor is selected through a nuclear power correction method. mode The nuclear power correction selector is controlled to select no correction; the nuclear power correction selector outputs N. E =0;

[0046] When the core power is stable, the input signal to the nuclear power plant's reactor power control system is corrected.

[0047] Correcting the input signals of the nuclear power plant reactor power control system includes two modes:

[0048] When automatic correction mode is selected, the nuclear power correction selector outputs N. E =N E2 ;

[0049] When manual correction mode is selected, the nuclear power correction selector outputs N. E =N E3 ;

[0050] Step 5, Nuclear power measurement signal N S 2 and nuclear power correction signal N E 12 is processed in adder 3 to obtain the control nuclear power signal N. C N C =N S +N E In step 4, the value N is manually corrected. E3 The method for determining it is as follows: based on the nuclear power measurement value N from the nuclear instrumentation system. S Real-time core neutron flux rate signal N from the core measurement system core And the actual operating status of the power plant, by manually inputting the correction value N. E3 This allows for the correction of the nuclear power signal. Considering signal validity and response time requirements, the measured nuclear power value N... S and real-time core neutron flux rate signal N core The data is transmitted via hardwired to the reactor power control system and then via network to the main control room display for reference when inputting manual correction values. In manual correction mode, the operator uses the real-time core neutron flux signal N... core Nuclear power measurement signal N S The size and relevant regulations for nuclear power plants provide a manual correction value N. E3 .

[0051] It will be apparent to those skilled in the art that the present invention is not limited to the details of the exemplary embodiments described above, and that the invention can be implemented in other specific forms without departing from its spirit or essential characteristics. Therefore, the embodiments should be considered in all respects as exemplary and non-limiting, and the scope of the invention is defined by the appended claims rather than the foregoing description. Thus, all variations falling within the meaning and scope of equivalents of the claims are intended to be included within the present invention. No reference numerals in the claims should be construed as limiting the scope of the claims.

[0052] Furthermore, it should be understood that although this specification describes embodiments, not every embodiment contains only one independent technical solution. This narrative style is merely for clarity. Those skilled in the art should consider the specification as a whole, and the technical solutions in each embodiment can also be appropriately combined to form other embodiments that can be understood by those skilled in the art.

Claims

1. A method for correcting the input signal of a nuclear power plant reactor power control system, characterized in that, Specifically, the steps include the following: S1. The reactor power control system acquires nuclear power measurement signals from the nuclear instrumentation system. and real-time core neutron flux rate signal from the core measurement system ; S2, the real-time core neutron flux rate signal and nuclear power measurement signals The initial power deviation signal is obtained by comparing the values ​​in the adder. The initial signal of the power deviation , ; S3, the initial signal of the power deviation The power deviation logic processor performs logic processing and outputs the result. The initial signal of the power deviation After passing through the dead-time function F(x), which sets the dead-time value to E, the power deviation signal... When the absolute value is greater than E, the calculation proceeds to the proportional coefficient K stage, and then the output is... Otherwise, the output is 0. S4. Select the correction method in the nuclear power correction selector according to the operating conditions and procedures, and output... ; To determine if the core power is stable, when the core power is unstable, a nuclear power correction method is selected. Control the nuclear power correction selector, select no correction, and the nuclear power correction selector outputs... =0; When the core power is stable, the input signal to the nuclear power plant's reactor power control system is corrected. Correcting the input signals of the nuclear power plant reactor power control system includes two modes: When automatic correction mode is selected, the nuclear power correction selector outputs... = ; When manual correction mode is selected, the nuclear power correction selector outputs... = ; S5, Nuclear Power Measurement Signal and nuclear power correction signal The operation is performed in the adder to obtain the control nuclear power signal. .

2. The method according to claim 1, characterized in that, The dead zone value E = 2%FP.

3. The method according to claim 2, characterized in that, The value of the proportional coefficient K is specifically determined by the nuclear power measurement signal. Upon entering the power deviation logic processor, K takes different values ​​depending on whether the nuclear power plant is in the high or low power range. When FP > 30%, K = 0; When ≤30%FP, K=1.

05.

4. The method according to claim 3, characterized in that, The value of the proportionality coefficient K is specifically as follows: .

5. The method according to claim 4, characterized in that, The The method for determining this is as follows: based on the nuclear power measurement signal from the nuclear instrumentation system. Real-time core neutron flux rate signal from the core measurement system In addition to the actual operating status of the power plant, correction values ​​are manually entered. .

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