Nuclear power correction factor automatic calculation method, device, medium and equipment

Abstract

The present application relates to a nuclear power correction factor automatic calculation method, device, medium and equipment, including the following steps: judging whether to start the correction factor calculation according to the trigger condition; obtaining the heat balance test report of KME and performing validity condition I judgment; calculating K nNEW and K nLSS , and performing validity condition II judgment according to the calculation result; calculating the current expected nuclear power of each channel, and performing validity condition III judgment according to the current expected nuclear power and the real-time nuclear power of each channel; judging whether to end the current calculation, if yes, determining K nNEW valid and ending the current calculation, if not, returning to continue calculation. The present application fundamentally solves the human error problem, significantly improves the reliability, and also improves the calculation efficiency, greatly shortens the calculation time.

Description

Technical Field

[0001] This invention relates to the field of nuclear power monitoring technology, and more specifically, to a method, apparatus, medium, and equipment for automatically calculating nuclear power correction factors. Background Technology

[0002] Nuclear power plants use an external nuclear instrumentation system (RPN) to measure and calculate nuclear power. The RPN has four independent channels (cabinets), each calculating the real-time nuclear power. This system involves the primary loop average thermal power P. KIC.1200Ath Based on the primary loop main pump speed and primary loop hot / cold pipe temperature signals over a 1200-second time period, the DCS system (Digital Control System for Nuclear Power Plant Units) calculates the average thermal power during that time period. This system also involves the secondary loop average thermal power P. KME.1200Ath Signal. Based on the inlet and outlet flow rate, pressure, and temperature signals of the steam generator secondary loop over a 1200-second time period, the KME system (Nuclear Power Plant Test Instrumentation Digital System) calculates the average thermal power during that time period. Generally, within the most recent 1200 seconds, if P RPN.1200A With P KIC.1200Ath If the deviation continues to exceed the limit, the nuclear power correction factor needs to be calculated. The calculated correction factor is K. nNEW .

[0003] Currently, nuclear power plants use manual methods to calculate nuclear power correction factors. However, manual calculation methods have problems such as long calculation time, low efficiency, high risk of human error, and insufficient validity criteria. Summary of the Invention

[0004] The technical problem to be solved by the present invention is to provide an automatic calculation method, apparatus, medium and device for nuclear power correction factor, which addresses the problems existing in the prior art.

[0005] The technical solution adopted by this invention to solve its technical problem is: to construct an automatic calculation method for nuclear power correction factor, comprising the following steps:

[0006] Step S1: Determine whether to start the correction factor calculation based on the triggering condition; if so, proceed to step S2.

[0007] Step S2: Obtain the KME thermal balance test report and determine the validity condition I. If the validity condition I is met, proceed to step S3; otherwise, stay in step S2.

[0008] Step S3: Calculation and The validity condition II is then determined based on the calculation results. If the validity condition II is met, step S4 is executed; otherwise, step S2 is returned.

[0009] Step S4: Calculate the current expected core power of each channel, and perform validity condition III judgment based on the current expected core power and the real-time core power of each channel. If validity condition III is met, proceed to step S5; otherwise, return to step S2.

[0010] Step S5: Determine whether to end this round of calculation. If yes, determine... If valid, end the current calculation; otherwise, return to step S4.

[0011] In the automatic calculation method for nuclear power correction factor described in this invention, step S2, obtaining the KME thermal balance test report and determining validity condition I, includes:

[0012] The timeliness of the heat balance test report generation time is assessed.

[0013] If the timeliness requirement is not met, then the validity condition I is deemed not to be met.

[0014] If the time of generation of the heat balance test report meets the timeliness requirement, then the heat balance test report shall be judged as qualified.

[0015] If the qualification requirement is not met, then the validity condition I is deemed not to be met.

[0016] If the heat balance test report meets the qualification requirements, then the KME test conditions are judged.

[0017] If the KME test conditions are not met, then the validity condition I is deemed not to be met.

[0018] If the KME test conditions are met, then the validity condition I is deemed to be met.

[0019] In the automatic calculation method for nuclear power correction factor described in this invention, the step of judging the pass / fail status of the thermal balance test report includes:

[0020] Obtain the current unit number, test completion time, and parameter information during the test;

[0021] Determine whether the current unit number is correct;

[0022] If the current unit number is incorrect, the qualification is deemed not to be met.

[0023] If the current unit number is correct, then determine whether the test completion time is within the time limit;

[0024] If the time is not within the specified time limit, then the qualification is deemed not to be met;

[0025] If the timeframe is within the specified time limit, then determine whether it falls within the set range based on the parameter information during the test period;

[0026] If it is not within the set range, it is determined that the qualification is not met;

[0027] If the condition falls within the specified range, it is determined that the condition is acceptable.

[0028] In the automatic calculation method for nuclear power correction factor described in this invention, the determination of KME test conditions includes:

[0029] Obtain the first set of condition signal trend values ​​and the second set of condition signal trend values ​​from the thermal balance test report;

[0030] Determine whether the trend values ​​of the first set of conditional signals meet the test conditions before and during the test, and whether the trend values ​​of the second set of conditional signals meet the test conditions during the test;

[0031] If yes, then the KME test conditions are met; otherwise, the KME test conditions are not met.

[0032] In the automatic calculation method for nuclear power correction factor described in this invention, step S3, which involves determining validity condition II based on the calculation results, includes:

[0033] Determine the Is it within the limit?

[0034] If not, then the validity condition II is not satisfied;

[0035] If so, then determine the stated With the Does the deviation exceed the limit?

[0036] If the limit is exceeded, then the validity condition II is not satisfied.

[0037] If there is no exceedance, then the validity condition II is deemed to be satisfied.

[0038] In the automatic calculation method for nuclear power correction factor described in this invention, step S4, which involves determining validity condition III based on the current expected nuclear power and the real-time nuclear power of each channel, includes:

[0039] Determine whether the current expected nuclear power is less than the set value;

[0040] If not, then the validity condition III is not satisfied;

[0041] If so, determine whether the deviation between the current expected nuclear power and the real-time nuclear power exceeds the limit;

[0042] If the limit is exceeded, then the validity condition III is not satisfied.

[0043] If there is no exceedance, then the validity condition III is deemed to be satisfied.

[0044] In the automatic calculation method for nuclear power correction factor described in this invention, step S5, determining whether to end the current round of calculation, includes:

[0045] Determine whether any one of the following is detected: stop calculation instruction, immediate calculation instruction, timeout trigger instruction, and hot / nuclear deviation trigger instruction;

[0046] If detected, the current round of calculation is considered complete;

[0047] If the stop calculation instruction, the immediate calculation instruction, the timeout trigger instruction, and the thermal / nuclear deviation trigger instruction are not detected, it is determined that the current round of calculation has not ended.

[0048] The present invention also provides an automatic calculation device for nuclear power correction factor, comprising: a human-computer interaction unit and a control unit;

[0049] The human-computer interaction unit is used to perform human-computer interaction operations and display them.

[0050] The control unit is used to perform the following steps:

[0051] Step S1: Determine whether to start the correction factor calculation based on the triggering condition; if so, proceed to step S2.

[0052] Step S2: Obtain the KME thermal balance test report and determine the validity condition I. If the validity condition I is met, proceed to step S3; otherwise, stay in step S2.

[0053] Step S3: Calculation and The validity condition II is then determined based on the calculation results. If the validity condition II is met, step S4 is executed; otherwise, step S2 is returned.

[0054] Step S4: Calculate the current expected core power of each channel, and perform validity condition III judgment based on the current expected core power and the real-time core power of each channel. If validity condition III is met, proceed to step S5; otherwise, return to step S2.

[0055] Step S5: Determine whether to end this round of calculation. If yes, determine... If valid, end the current calculation; otherwise, return to step S4.

[0056] The present invention also provides a storage medium storing a computer program adapted for loading by a processor to execute the steps of the automatic calculation method for the nuclear power correction factor as described above.

[0057] The present invention also provides an electronic device, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the automatic calculation method for nuclear power correction factor as described above by calling the computer program stored in the memory.

[0058] The automatic calculation method, apparatus, medium, and device for nuclear power correction factors according to the present invention have the following beneficial effects: It includes the following steps: determining whether to initiate correction factor calculation based on triggering conditions; obtaining a thermal balance test report and performing validity condition I judgment; calculating... and The calculation results are used to determine validity condition II; the current expected core power of each channel is calculated, and validity condition III is determined based on the current expected core power and the real-time core power of each channel; the calculation is then stopped to determine whether to end the current round of calculation. If valid, the current calculation round ends; otherwise, it returns to continue calculation. This invention fundamentally solves the problem of human error, significantly improves reliability, and also improves computational efficiency, greatly shortening computation time. Attached Figure Description

[0059] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings:

[0060] Figure 1 This is a flowchart illustrating the automatic calculation method for nuclear power correction factor provided in an embodiment of the present invention;

[0061] Figure 2 This is a system structure diagram of the automatic nuclear power correction factor calculation device provided in the embodiments of the present invention;

[0062] Figure 3 This is a schematic diagram of the calculation screen of the automatic calculation device for nuclear power correction factor provided in an embodiment of the present invention. Detailed Implementation

[0063] 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.

[0064] To address the problems of long calculation time, low efficiency, the need for multiple people to perform the calculation, high risk of human error, and insufficient criteria for the validity of the calculated nuclear power correction factor in the current method of manually calculating nuclear power correction factor in nuclear power plants, this invention provides an automatic calculation method for nuclear power correction factor.

[0065] refer to Figure 1 , Figure 1 A preferred embodiment of the automatic calculation method for nuclear power correction factor provided by the present invention is shown.

[0066] Specifically, such as Figure 1 As shown, the automatic calculation method for the nuclear power correction factor may include the following steps: S1, S2, S3, S4, and S5. The specific details of each step are as follows:

[0067] Step S1: Determine whether to start the correction factor calculation based on the triggering condition. If so, proceed to step S2.

[0068] In some embodiments, the calculation of the nuclear power correction factor (hereinafter referred to as the K value for ease of explanation) can be triggered manually or automatically. Manual triggering can be initiated by a user (such as a nuclear power plant operator) clicking the corresponding control on the operating interface, while automatic triggering can be initiated by a pre-defined program (such as timed triggering or limit triggering). The triggering conditions (or triggering methods) can include four types: immediate calculation, stop calculation, timed calculation, and large thermal / nuclear deviation. Immediate calculation and stop calculation can be triggered manually by the user, while timed calculation and large thermal / nuclear deviation are triggered automatically. Both the large thermal / nuclear deviation and timed calculation modes can be selected simultaneously, with the interval between adjacent triggers not less than one KME (Nuclear Power Plant Test Instrument Digital System) thermal balance test duration. That is, if both triggering conditions are triggered simultaneously or the trigger interval is less than one KME thermal balance test duration, a single calculation is performed; if it is an interval trigger and the interval is greater than one KME thermal balance test duration, the calculations are performed separately.

[0069] Step S2: Obtain the KME thermal balance test report and determine the validity condition I. If the validity condition I is met, proceed to step S3; otherwise, stay in step S2.

[0070] In some embodiments, step S2, obtaining the KME thermal balance test report and determining validity condition I includes: determining the timeliness of the thermal balance test report generation time; if the timeliness is not met, then validity condition I is not met; if the thermal balance test report generation time meets the timeliness, then the thermal balance test report is determined to be qualified; if the qualification is not met, then validity condition I is not met; if the thermal balance test report is qualified, then KME test condition determination is performed; if the KME test conditions are not met, then validity condition I is not met; if the KME test conditions are met, then validity condition I is met.

[0071] Preferably, in this embodiment of the invention, the qualification judgment of the heat balance test report includes: obtaining the current unit number, test completion time, and parameter information during the test; determining whether the current unit number is correct; if the current unit number is incorrect, then the qualification is not met; if the current unit number is correct, then determining whether the test completion time is within the time limit; if it is not within the time limit, then the qualification is not met; if it is within the time limit, then determining whether it is within the set range based on the parameter information during the test; if it is not within the set range, then the qualification is not met; if it is within the set range, then the qualification is met.

[0072] Preferably, in this embodiment of the invention, the KME test condition judgment includes: obtaining the first set of condition signal trend values ​​and the second set of condition signal trend values ​​in the thermal balance test report; judging whether the first set of condition signal trend values ​​meets the test conditions before and during the test, and whether the second set of condition signal trend values ​​meets the test conditions during the test; if yes, it is judged that the KME test conditions are met, otherwise, it is judged that the KME test conditions are not met.

[0073] Optionally, in some embodiments, the thermal equilibrium test report can be stored in the KME system in the form of a dataset or in the form of a report. The following explanation uses a report as an example.

[0074] In this step, the control unit (such as a controller) reads the thermal equilibrium test report from the KME system. Next, after reading the report, validity condition I is determined, and the specific determination includes:

[0075] (1) Timeliness judgment:

[0076] Determine whether the retrieved report is a recent, unused test report generated within the last 4 hours by the KME system. "Unused" means that the report has not yet been used to calculate the nuclear power correction factor. If it is a recent, unused test report generated within the last 4 hours by the KME system, the timeliness requirement is met; otherwise, the timeliness requirement is not met, and validity condition I is not met.

[0077] (2) Qualification judgment:

[0078] The pass / fail status of the read KME report can be determined by reviewing the key items in the heat balance test report. These key items include:

[0079] Unit Number: The current unit number;

[0080] Test completion time: within the last 4 hours;

[0081] Parameter information during the test: During the test, the differential pressure of the feed water in the second circuit of the steam generator, the feed water temperature, the feed water pressure, the steam pressure, and the blowdown flow rate were all within the set range; at the same time, the difference between the values ​​of each steam generator was within the set range.

[0082] If the unit number is the current unit number, the test completion time is within the last 4 hours, and the feedwater pressure difference, feedwater temperature, feedwater pressure, steam pressure, and blowdown flow rate of the steam generator's secondary circuit are all within the set range during the test, and the difference between each steam generator is within the set range, then the test is deemed to meet the qualification requirements.

[0083] (3) Judgment of KME test conditions:

[0084] For determining the KME test conditions, the trend values ​​of the first set of condition signals must be met both before and during the test, while the trend values ​​of the second set of condition signals must be met only during the test. The trend values ​​of the first set of condition signals include the following two items: a) and b)

[0085] a) Before the KME test (which can be set) and during the test, the quality of the primary loop thermal power or nuclear power signal is good, and the difference between the maximum and minimum values ​​does not exceed the limit;

[0086] b) Before the KME test (which can be set) and during the test, the quality of the dual-circuit power signal is good and the difference between the maximum and minimum values ​​does not exceed the limit.

[0087] The second set of conditional signal trend values ​​includes the following c) ~ l):

[0088] c) During the test, the turbine speed variation remained within the set range;

[0089] d). During the test, the steam generator liquid level was in automatic adjustment mode, and the deviation between the actual liquid level of each evaporator and the set value did not exceed the limit;

[0090] e). During the test, the pressure regulator was in automatic adjustment mode, and the deviation between the actual pressure value and the set value did not exceed the limit;

[0091] f) During the test, the pressure regulator level was in automatic control mode, and the deviation between the actual level and the set value did not exceed the limit;

[0092] g). During the test, the deviation between the average temperature of the reactor coolant and the reference temperature did not exceed the limit;

[0093] h). During the experiment, the primary loop nuclear power or primary loop thermal power remained stable above 50%FP;

[0094] i) No tests that could affect nuclear power stability were conducted during the experiment, such as RPN, RPR (reactor protection system), and RPCC (reactor power regulation system) tests;

[0095] j). During the experiment, the power of each RPN core ( P nRPN The quality is "good";

[0096] k). During the test, the current quality of the upper and lower segments of each RPN channel collected from the LSS system (coolant loss accident monitoring system) was "good";

[0097] l). During the test, no RPN channels were tested, no faults were found, the high voltage was normal, and the KIC lifecycle signal was normal.

[0098] If the timeliness, compliance, and KME test conditions are all met, then the validity condition I is deemed to be met, and the process proceeds to step S3; otherwise, the process remains at this step and continues to periodically obtain and evaluate reports.

[0099] Step S3: Calculation and The validity condition II is then determined based on the calculation results. If the validity condition II is met, step S4 is executed; otherwise, step S2 is returned.

[0100] In some embodiments, step S3, determining validity condition II based on the calculation result, includes: determining... Is it within the limit? If not, then validity condition II is not met; if yes, then... and Check whether the deviation exceeds the limit; if it does, then the validity condition II is not met; if it does not exceed the limit, then the validity condition II is met.

[0101] In this step, the first calculation is... and .in, This is a new core power correction factor for a certain RPN channel. This is the nuclear power correction factor calculated based on LSS data.

[0102] Calculated using the following formula:

[0103] ;

[0104] in, K MAX >= K nNEW >= K MIN , K MAX , K MIN It is a constant; Let n be a new core power correction factor for a certain RPN channel, where n is 1, 2, 3, 4, ..., representing a certain RPN channel; This represents the average thermal power of the secondary loop over a 1200-second time period. This data is calculated by KME based on the inlet / outlet pressure, temperature, and flow rate of the evaporator secondary loop. th represents the thermal power. It can be read directly from the report; This represents the average core power of a certain RPN channel over a 1200-second time period. K nOLD This indicates the current (or old) nuclear power correction factor for a certain RPN channel, which is stored in the DCS (Digital Control System for Nuclear Power Plant Units). The most recent K value should be used. nOLD Calculate K nNEW .

[0105] Calculated using the following formula:

[0106]

[0107] Calculated using the following formula:

[0108]

[0109] in, and These are statistical values ​​for the same time period; This is the core power correction factor calculated based on LSS data for a certain RPN channel, where n is 1, 2, 3, 4, ..., representing a certain RPN channel; This represents the average RPN core power over a 1200-second time period, calculated based on LSS-acquired data. The specific calculation formula is as follows:

[0110]

[0111] Among them, P nLSS According to I nLSS1 ~I nLSS6 The calculated RPN core power is shown in the following formula:

[0112] ;

[0113] in, K nH , K nB These are the current / core power conversion coefficients for the upper and lower segments of a certain RPN channel, respectively. nLSS1 ~I nLSS6 The currents of the upper and lower segments of a certain RPN channel collected by the LSS system, where I nLSS1 ~I nLSS3These are the currents of three detectors in the upper section of a certain RPN channel, I. nLSS4 ~I nLSS6 These represent the currents of the three detectors in the lower section of the channel.

[0114] Calculated K nNEW and K nLSS Next, perform the validity condition II judgment, which includes the following:

[0115] (1) K nNEW Not exceeded (i.e.) K MAX >= K nNEW >= K MIN );

[0116] (2) K nNEW , K nLSS The deviation between them did not exceed the limit, that is K nNEW , K nLSS The difference between them is within the preset range.

[0117] if K nNEW Not exceeded, and K nNEW , K nLSS If the deviation between the two is within the limit, then the validity condition II is satisfied and the process proceeds to step S4; otherwise, the process returns to step S2.

[0118] Step S4: Calculate the current expected core power of each channel, and perform validity condition III judgment based on the current expected core power and the real-time core power of each channel. If validity condition III is met, proceed to step S5; otherwise, return to step S2.

[0119] In some embodiments, step S4, determining validity condition III based on the current expected core power and the real-time core power of each channel includes: determining whether the current expected core power is less than a set value; if not, determining that validity condition III is not met; if yes, determining whether the deviation between the current expected core power and the real-time core power exceeds the limit; if it exceeds the limit, determining that validity condition III is not met; if it does not exceed the limit, determining that validity condition III is met.

[0120] In this step, firstly, the current expected nuclear power is calculated; after the calculation, validity condition III is determined.

[0121] Among them, the current expected nuclear power is calculated by the following formula:

[0122]

[0123] Among them, is the expected nuclear power calculated according to K nNEW (i.e., the current expected nuclear power); P nRPN.exp <a1, where a1 is a constant.

[0124] After calculating judge whether it exceeds the limit, that is, whether it satisfies P nRPN.exp <a1. If it satisfies P nRPN.exp <a1, and P nRPN.exp 、P nRPN the deviation between them does not exceed the limit (i.e., 2, where a2 is a constant), then it is determined that the validity condition III is satisfied, and proceed to step S5. Otherwise, return to step S2. P nRPN is the real-time nuclear power, that is, the real-time nuclear power (dimensionless %FP) of a certain RPN channel at a certain moment; represents taking the absolute value.

[0125] P nRPN can be calculated by the following formula:

[0126] ;

[0127] G is a constant, with a value of 1.0E+6; K nH 、 K nB are the current / nuclear power conversion coefficients of the upper and lower segments of a certain RPN channel respectively; K n is the nuclear power correction factor of a certain RPN channel; I n1 ~I n6 are the currents of the upper and lower segments of a certain RPN channel collected by the LSS system.

[0128] Step S5: Judge whether to end this round of calculation. If so, determine valid and end this round of calculation. If not, return to step S4.

[0129] In some embodiments, step S5, determining whether to end the current round of calculation includes: determining whether any one of the following is detected: a stop calculation instruction, an immediate calculation instruction, a timeout trigger instruction, and a hot / nuclear deviation trigger instruction; if detected, the current round of calculation is determined to be over; if no stop calculation instruction, immediate calculation instruction, timeout trigger instruction, or hot / nuclear deviation trigger instruction is detected, the current round of calculation is determined not to be over.

[0130] Specifically, in this step, if any of the following termination methods occur, the current round of calculation is considered complete, and the process returns to step S1; if none of the following termination methods occur, the process returns to step S4. The termination methods are as follows:

[0131] 1) The operator presses the stop calculation button on the dedicated DCS screen (i.e., triggers the stop calculation command);

[0132] 2) The operator presses the "Calculate Now" button on the dedicated DCS screen (which triggers the "Calculate Now" command).

[0133] 3) The timing in step S1 expires, or the thermal / nuclear deviation is large.

[0134] The automatic calculation method for nuclear power correction factor of the present invention fundamentally solves the problem of the impact of human error (such as data sampling error, calculation error, etc.) caused by manual methods on the calculation results, and improves the accuracy of calculation. It makes up for the defects of the original method in judging the validity of nuclear power correction factor, and improves the reliability of calculation. At the same time, compared with the original method which requires multiple people and at least 2 hours to complete a calculation, the present invention completes a calculation in less than 1 minute, which greatly shortens the calculation time and significantly improves the calculation efficiency.

[0135] refer to Figure 2 The present invention also provides an automatic calculation device for nuclear power correction factor.

[0136] like Figure 2 As shown, the automatic nuclear power correction factor calculation device includes a human-computer interaction unit and a control unit.

[0137] The human-computer interaction unit is used to perform human-computer interaction operations and display information.

[0138] The control unit is used to perform the following steps: Step S1: Determine whether to start the correction factor calculation based on the trigger condition; if yes, proceed to step S2; Step S2: Obtain the KME thermal balance test report and perform validity condition I judgment; if validity condition I is met, proceed to step S3; otherwise, remain in step S2; Step S3: Calculate... and The calculation results are used to determine validity condition II. If validity condition II is met, proceed to step S4; otherwise, return to step S2. Step S4: Calculate the current expected core power for each channel and determine validity condition III based on the current expected core power and the real-time core power for each channel. If validity condition III is met, proceed to step S5; otherwise, return to step S2. Step S5: Determine whether to end this round of calculation. If yes, determine... If valid, end the current calculation; otherwise, return to step S4.

[0139] Figure 2 In this context, the DCS is the digital control system for nuclear power plant units, equipped with operator stations. These operator stations display dedicated screens for calculating nuclear power correction factors (e.g., ...). Figure 3 (As shown). Operators monitor the calculation process of the K parameter (i.e., nuclear power correction factor) through this screen. The KME is a digital instrumentation system for nuclear power plant testing, featuring automatic periodic core thermal balance testing. After the test, test results are generated and saved in reports or other formats. The controller (i.e., control unit) is used to calculate the K parameter, and the touchscreen is for maintenance personnel to use for parameter modification and fault diagnosis. All devices / systems are connected via a network, and isolators are used for electrical isolation between devices / systems.

[0140] like Figure 3 As shown, Figure 3 The three indicator lights on the left are used to indicate the calculation process. When in step S1, the "Trigger" indicator light is on; when in step S2, the "KME Report" indicator light is on; when in steps S3 to S5, the "Calculation" indicator light is on. K nNEW If any of the validity conditions I, II, or III are not met, each RPN channel K nNEW The display border is flashing red. Figure 3 The diagram shows four RPN channels (RPN010MA, RPN020MA, RPN030MA, and RPN040MA). For example... Figure 3 As shown, when the operator presses the "Calculate Now" button on the DCS dedicated screen, steps S1 and S5 are effective; when the operator presses the "Stop Calculation" button on the DCS dedicated screen, the calculation is immediately stopped and the process returns to step S1; when the thermal / nuclear deviation exceeds the limit, the calculation is triggered and the thermal / nuclear deviation exceedance calculation mode is entered; when the set time is reached, the "Timed Calculation" mode is triggered.

[0141] Specifically, the specific coordination and operation process between the various units in the automatic nuclear power correction factor calculation device can be referred to the above-mentioned automatic nuclear power correction factor calculation method, and will not be repeated here.

[0142] Furthermore, an electronic device according to the present invention includes a memory and a processor; the memory is used to store a computer program; the processor is used to execute the computer program to implement the automatic calculation method for the nuclear power correction factor as described above. Specifically, according to embodiments of the present invention, the processes described above with reference to the flowchart can be implemented as computer software programs. For example, embodiments of the present invention include a computer program product comprising a computer program carried on a computer-readable medium, the computer program containing program code for performing the methods shown in the flowchart. In such embodiments, when the computer program is downloaded, installed, and executed by an electronic device, it performs the functions defined in the methods of the embodiments of the present invention. The electronic device in the present invention can be a terminal such as a laptop, desktop computer, tablet computer, or smartphone, or it can be a server.

[0143] Furthermore, one type of storage medium of the present invention stores a computer program thereon, which, when executed by a processor, implements the automatic calculation method for the nuclear power correction factor described above. Specifically, it should be noted that the storage medium described above in the present invention can be a computer-readable signal medium or a computer-readable storage medium, or any combination thereof. A computer-readable storage medium can be, for example, but not limited to, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any combination thereof. More specific examples of a computer-readable storage medium may include, but are not limited to: an electrical connection having one or more wires, a portable computer disk, a hard disk, random access memory (RAM), read-only memory (ROM), erasable programmable read-only memory (EPROM or flash memory), optical fiber, portable compact disk read-only memory (CD-ROM), optical storage device, magnetic storage device, or any suitable combination thereof. In the present invention, a computer-readable storage medium can be any tangible medium containing or storing a program that can be used by or in conjunction with an instruction execution system, apparatus, or device. In the present invention, a computer-readable signal medium can include a data signal propagated in baseband or as part of a carrier wave, wherein computer-readable program code is carried. The transmitted data signal can take various forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination thereof. The computer-readable signal medium can also be any computer-readable medium other than a computer-readable storage medium, which can send, propagate, or transmit a program for use by or in connection with an instruction execution system, apparatus, or device. The program code contained on the computer-readable medium can be transmitted using any suitable medium, including but not limited to: wires, optical fibers, RF (radio frequency), etc., or any suitable combination thereof.

[0144] The aforementioned computer-readable medium may be included in the aforementioned electronic device; or it may exist independently and not assembled into the electronic device.

[0145] The various embodiments in this specification are described in a progressive manner, with each embodiment focusing on its differences from other embodiments. Similar or identical parts between embodiments can be referred to interchangeably. For the apparatus disclosed in the embodiments, since they correspond to the methods disclosed in the embodiments, the description is relatively simple; relevant parts can be referred to the method section.

[0146] Those skilled in the art will further recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of both. To clearly illustrate the interchangeability of hardware and software, the components and steps of the various examples have been generally described in terms of functionality in the foregoing description. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementations should not be considered beyond the scope of this invention.

[0147] The steps of the methods or algorithms described in conjunction with the embodiments disclosed herein can be implemented directly by hardware, a software module executed by a processor, or a combination of both. The software module can be located in random access memory (RAM), main memory, read-only memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art.

[0148] The above embodiments are only for illustrating the technical concept and features of the present invention, and are intended to enable those skilled in the art to understand the content of the present invention and implement it accordingly. They do not limit the scope of protection of the present invention. All equivalent changes and modifications made within the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. An automatic calculation method for nuclear power correction factor, characterized in that, Includes the following steps: Step S1: Determine whether to start the correction factor calculation based on the triggering condition; if so, proceed to step S2. Step S2: Obtain the KME thermal balance test report and determine the validity condition I. If the validity condition I is met, proceed to step S3; otherwise, stay in step S2. Step S3: Calculation and The validity condition II is then determined based on the calculation results. If the validity condition II is met, step S4 is executed; otherwise, step S2 is returned. In step S3, the validity condition II judgment based on the calculation results includes: Determine the Is it within the limit? If not, then the validity condition II is not satisfied; If so, then determine the stated With the Does the deviation exceed the limit? If the limit is exceeded, then the validity condition II is not satisfied. If there is no exceedance, then the validity condition II is deemed to be satisfied; Step S4: Calculate the current expected core power of each channel, and perform validity condition III judgment based on the current expected core power and the real-time core power of each channel. If validity condition III is met, proceed to step S5; otherwise, return to step S2. Step S5: Determine whether to end this round of calculation. If yes, determine... If valid, end the current calculation; otherwise, return to step S4.

2. The automatic calculation method for nuclear power correction factor according to claim 1, characterized in that, In step S2, obtaining the KME thermal balance test report and determining the validity condition I includes: The timeliness of the generation time of the aforementioned heat balance test report is assessed. If the timeliness requirement is not met, then the validity condition I is deemed not to be met. If the time of generation of the heat balance test report meets the timeliness requirement, then the heat balance test report shall be judged as qualified. If the qualification requirement is not met, then the validity condition I is deemed not to be met. If the heat balance test report meets the qualification requirements, then the KME test conditions are judged. If the KME test conditions are not met, then the validity condition I is deemed not to be met. If the KME test conditions are met, then the validity condition I is deemed to be met.

3. The automatic calculation method for nuclear power correction factor according to claim 2, characterized in that, The process of determining the pass / fail status of the heat balance test report includes: Obtain the current unit number, test completion time, and parameter information during the test; Determine whether the current unit number is correct; If the current unit number is incorrect, the qualification is deemed not to be met. If the current unit number is correct, then determine whether the test completion time is within the time limit; If the time is not within the specified time limit, then the qualification is deemed not to be met; If the timeframe is within the specified time limit, then determine whether it falls within the set range based on the parameter information during the test period; If it is not within the set range, it is determined that the qualification is not met; If the condition falls within the specified range, it is determined that the condition is acceptable.

4. The automatic calculation method for nuclear power correction factor according to claim 2, characterized in that, The conditions for conducting the KME test include: Obtain the first set of condition signal trend values ​​and the second set of condition signal trend values ​​from the thermal balance test report; Determine whether the trend values ​​of the first set of conditional signals meet the test conditions before and during the test, and whether the trend values ​​of the second set of conditional signals meet the test conditions during the test; If yes, then the KME test conditions are met; otherwise, the KME test conditions are not met.

5. The automatic calculation method for nuclear power correction factor according to claim 1, characterized in that, In step S4, the validity condition III judgment based on the current expected nuclear power and the real-time nuclear power of each channel includes: Determine whether the current expected nuclear power is less than the set value; If not, then the validity condition III is not satisfied; If so, determine whether the deviation between the current expected nuclear power and the real-time nuclear power exceeds the limit; If the limit is exceeded, then the validity condition III is not satisfied. If there is no exceedance, then the validity condition III is deemed to be satisfied.

6. The automatic calculation method for nuclear power correction factor according to claim 1, characterized in that, In step S5, determining whether to end the current round of calculation includes: Determine whether any one of the following is detected: stop calculation instruction, immediate calculation instruction, timeout trigger instruction, and hot / nuclear deviation trigger instruction; If detected, the current round of calculation is considered complete; If the stop calculation instruction, the immediate calculation instruction, the timeout trigger instruction, and the thermal / nuclear deviation trigger instruction are not detected, it is determined that the current round of calculation has not ended.

7. An automatic calculation device for nuclear power correction factor, characterized in that, Includes: a human-computer interaction unit and a control unit; The human-computer interaction unit is used to perform human-computer interaction operations and display them. The control unit is used to perform the following steps: Step S1: Determine whether to start the correction factor calculation based on the triggering condition; if so, proceed to step S2. Step S2: Obtain the KME thermal balance test report and determine the validity condition I. If the validity condition I is met, proceed to step S3; otherwise, stay in step S2. Step S3: Calculation and The validity condition II is then determined based on the calculation results. If the validity condition II is met, step S4 is executed; otherwise, step S2 is returned. In step S3, the validity condition II judgment based on the calculation results includes: Determine the Is it within the limit? If not, then the validity condition II is not satisfied; If so, then determine the stated With the Does the deviation exceed the limit? If the limit is exceeded, then the validity condition II is not satisfied. If there is no exceedance, then the validity condition II is deemed to be satisfied; Step S4: Calculate the current expected core power of each channel, and perform validity condition III judgment based on the current expected core power and the real-time core power of each channel. If validity condition III is met, proceed to step S5; otherwise, return to step S2. Step S5: Determine whether to end this round of calculation. If yes, determine... If valid, end the current calculation; otherwise, return to step S4.

8. A storage medium, characterized in that, The storage medium stores a computer program adapted for loading by a processor to perform the steps of the automatic calculation method for nuclear power correction factors as described in any one of claims 1 to 6.

9. An electronic device, characterized in that, It includes a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the automatic calculation method for nuclear power correction factor as described in any one of claims 1 to 6 by calling the computer program stored in the memory.

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