A method and system for automatically diagnosing a leakage rate of a primary loop of a nuclear power plant

Abstract

The present application relates to a kind of nuclear power plant one loop leakage rate automatic diagnosis method and system.The method comprises the following steps: S1, whether the one loop meets the initial condition of starting coolant leakage rate calculation is monitored and judged;If yes, execute step S2, if no, continue to monitor and judge whether the one loop meets the initial condition of starting coolant leakage rate calculation until the initial condition of starting coolant leakage rate calculation is met;S2, the liquid level of the one loop stabilizer and initial liquid level are obtained, and the coolant leakage rate is started to be calculated, and the calculation result of the coolant leakage rate is obtained;And whether the calculation result of the coolant leakage rate exceeds the preset leakage rate limit value is judged;If yes, accident procedure early warning information is sent out.The technical scheme of the present application can realize one loop coolant leakage rate calculation entry and initial condition self-diagnosis, automatic calculation and judgment, reduce the risk of human error, improve the efficiency of accident handling and the safety of nuclear power plant.

Description

Technical Field

[0001] This invention relates to the field of nuclear power plant safety technology, and more specifically, to an automatic diagnostic method and system for the primary loop leakage rate of a nuclear power plant. Background Technology

[0002] Among the many systems in a nuclear power plant, the primary loop system is a crucial barrier to ensure nuclear safety. To prevent the leakage of radioactive materials from the primary loop, extensive analysis and corresponding procedures are developed during the nuclear power plant design process. Minor breaches in the primary loop are often controlled through accident operation procedures. However, in actual implementation, operators need to manually calculate and determine the primary loop leakage rate based on liquid level changes. This calculation process requires operators to manually determine the calculation needs, manually collect and record relevant parameters, and manually calculate the results. Consequently, obtaining the calculation results takes a considerable amount of time, which is detrimental to accident handling.

[0003] Furthermore, manually collecting and recording leakage rate calculation parameters by operators requires a certain recording time, and the recorded parameters may deviate from the actual parameters. There is also the possibility of parameter recording errors, posing a significant risk of human error. Therefore, quickly calculating and determining the leakage rate has become a concern for nuclear power plant designers. Summary of the Invention

[0004] The technical problem to be solved by this invention is to realize the automatic calculation and judgment of the primary loop leakage rate, improve the efficiency of accident handling, and provide an automatic diagnosis method and system for the primary loop leakage rate of nuclear power plants.

[0005] The technical solution adopted by this invention to solve its technical problem is: to construct an automatic diagnostic method for the primary loop leakage rate of a nuclear power plant, the method comprising:

[0006] S1. Monitor and determine whether the primary circuit meets the initial conditions for calculating the start-up coolant leakage rate; if yes, proceed to step S2; if no, continue to monitor and determine whether the primary circuit meets the initial conditions for calculating the start-up coolant leakage rate until the initial conditions for calculating the start-up coolant leakage rate are met.

[0007] S2. Obtain the liquid level and initial liquid level of the primary circuit voltage regulator, and start calculating the coolant leakage rate to obtain the calculation result of the coolant leakage rate; and determine whether the calculation result of the coolant leakage rate exceeds the preset leakage rate limit; if so, issue an accident procedure warning message.

[0008] Preferably, the automatic diagnostic method further includes: determining whether a radioactive alarm signal has occurred; if so, then performing step S1.

[0009] Preferably, step S1 includes:

[0010] S1-1: Determine whether the temperature of the core in the primary loop core measurement system exceeds a preset temperature threshold.

[0011] Determine whether the power load of the steam turbine generator exceeds the preset power threshold;

[0012] When the temperature of the reactor core exceeds the temperature threshold and / or the power load exceeds the power threshold, step S1-2 is executed;

[0013] S1-2: Determine that the charging and discharging circuit is in an isolated state;

[0014] The primary sampling pipeline is in an isolated state; and

[0015] When the primary loop boron and water supply system is in manual mode and shut down, it is determined that the primary loop meets the initial conditions for calculating the coolant leakage rate.

[0016] Preferably, step S2 includes the following steps:

[0017] S2-1: Obtain the initial liquid level L0 of the primary circuit voltage regulator and record the initial liquid level L0 at the start of the calculation;

[0018] S2-2: Obtain the current liquid level L1 at the current time t1 according to the set rules;

[0019] S2-3: Calculate the coolant leakage rate at the current time based on the initial liquid level L0, the current time t1, and the current liquid level L1.

[0020] Preferably, in step S2-2, the setting rule includes: inputting a trigger signal at a set interval to trigger the acquisition of the current liquid level L1, and recording the trigger time as the current time t1; or

[0021] The current liquid level L1 is automatically read at set time intervals, and the reading time is recorded as the current time t1.

[0022] Preferably, in steps S2-3, the coolant leakage rate is calculated using Qleak = 3.464 * (L0 - L1) / ((t1 - t0) + 0.23).

[0023] Preferably, step S2 further includes:

[0024] S2-4: Determine whether the current liquid level L1 is greater than the first liquid level limit. If so, determine that the coolant leakage rate meets the limit requirements.

[0025] If not, determine whether the current liquid level L1 is less than the second liquid level limit; if so, calculate the coolant leakage rate.

[0026] If the current liquid level L1 is between the first liquid level limit and the second liquid level limit, a time delay is set, and the liquid level at the next moment is obtained as the current liquid level L1, and then a judgment is made.

[0027] Preferably, in step S2-2, the liquid level of the primary circuit regulator is read, and it is determined whether the liquid level of the regulator is displayed as a readable normal value;

[0028] If the liquid level display of the voltage regulator is a readable normal value, it is determined that the source signal is valid, and the liquid level of the first-loop voltage regulator is recorded as the current liquid level L1;

[0029] If the liquid level of the pressure regulator is not displayed as a readable normal value, it is determined that the source signal is invalid, and the first loop suspends the calculation of the coolant leakage rate.

[0030] This invention also provides an automatic diagnostic system for primary loop leakage rate in nuclear power plants, employing any of the automatic diagnostic methods described above. The automatic diagnostic system includes:

[0031] The monitoring module is used to monitor and determine whether the primary loop meets the initial conditions for calculating the start-up coolant leakage rate;

[0032] The calculation module is used to read the liquid level of the primary circuit regulator, start the coolant leakage rate calculation, and obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula.

[0033] The early warning module is used to determine whether the calculated result of the coolant leakage rate exceeds the preset leakage rate limit; if so, it issues an accident procedure early warning message.

[0034] Preferably, the monitoring module further includes:

[0035] The first monitoring submodule is used to monitor and determine whether the temperature of the core in the primary loop core measurement system exceeds a preset temperature threshold.

[0036] The second monitoring submodule is used to monitor and determine whether the power load of the steam turbine generator exceeds the preset power threshold.

[0037] The third monitoring submodule is used to monitor and determine whether the charging and discharging of the primary circuit is in an isolated state.

[0038] The fourth monitoring submodule is used to monitor and determine whether the primary loop sampling pipeline is in an isolated state;

[0039] The fifth monitoring submodule is used to monitor and determine whether the primary loop boron and water supply system is in manual mode and shut down.

[0040] Preferably, the computing module further includes:

[0041] The reading submodule is used to read the liquid level of the primary circuit regulator, start the coolant leakage rate calculation, and record the initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation.

[0042] The calculation submodule is used to set the delay time, record the real-time liquid level L1 of the pressure regulator and the real-time time t1 of the coolant leakage rate calculation, obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula, and determine whether the real-time liquid level L1 of the pressure regulator is less than the initial liquid level L0 of the pressure regulator.

[0043] Preferably, the reading submodule is further configured to read the liquid level of the primary circuit regulator and determine whether the liquid level of the regulator is displayed as a readable normal value; the source signal for initiating the coolant leakage rate calculation is the liquid level of the regulator;

[0044] If the liquid level display of the pressure regulator is a readable normal value, it is determined that the source signal is valid. The first loop starts the coolant leakage rate calculation and records the initial liquid level L0 of the pressure regulator and the initial time t0 of the coolant leakage rate calculation.

[0045] If the liquid level of the pressure regulator is not displayed as a readable normal value, it is determined that the source signal is invalid, and the first loop suspends the calculation of the coolant leakage rate.

[0046] Preferably, the computing submodule further includes:

[0047] The first calculation submodule is used to set a time delay, continue to read the liquid level of the primary circuit regulator to obtain the rate of change of the liquid level of the regulator, and record the real-time liquid level L1 of the regulator and the real-time time t1 of the coolant leakage rate calculation. According to the coolant leakage rate calculation formula, the calculation result of the coolant leakage rate is obtained.

[0048] Based on the recorded real-time liquid level L1 and the initial liquid level L0 of the voltage regulator, determine whether the real-time liquid level L1 of the voltage regulator is less than the initial liquid level L0 of the voltage regulator.

[0049] If so, the liquid level of the pressure regulator drops, and based on the obtained rate of change of the liquid level of the pressure regulator, it is determined whether the drop in the liquid level of the pressure regulator exceeds the preset liquid level change limit; if not, the liquid level of the pressure regulator rises or remains unchanged, and it is determined that the coolant leakage rate does not exceed the preset leakage rate limit.

[0050] The second calculation submodule is used to determine whether the drop in the liquid level of the regulator exceeds a preset liquid level change limit based on the obtained rate of change of the liquid level of the regulator when it is determined that the real-time liquid level L1 of the regulator is less than the initial liquid level L0 of the regulator.

[0051] If yes, proceed to step S3; if no, set a delay time, and during the delay time, continue to read the liquid level of the primary circuit regulator to obtain the rate of change of the liquid level of the regulator; when the delay time ends, determine whether the drop in the liquid level of the regulator exceeds the preset liquid level change limit based on the obtained rate of change of the liquid level of the regulator.

[0052] The third calculation submodule is used to set a delay time when determining whether the drop in the liquid level of the regulator exceeds the preset liquid level change limit. During the delay time, the liquid level of the primary circuit regulator is continued to be read to obtain the rate of change of the liquid level of the regulator.

[0053] When the delay time ends, based on the obtained rate of change of the liquid level of the regulator, it is further determined whether the drop in the liquid level of the regulator exceeds the preset liquid level change limit.

[0054] If yes, proceed to step S3; if no, determine that the coolant leakage rate does not exceed the preset leakage rate limit.

[0055] The fourth calculation submodule is used to read the liquid level of the primary circuit regulator, restart the coolant leakage rate calculation, and keep the recorded initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation unchanged.

[0056] Set a timeout period and re-record the real-time liquid level L1 of the voltage regulator and the real-time time t1 for calculating the coolant leakage rate; obtain the calculated result of the coolant leakage rate according to the coolant leakage rate calculation formula; or

[0057] Used to read the liquid level of the primary circuit regulator, restart the coolant leakage rate calculation, and re-record the initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation;

[0058] Set a timeout period and re-record the real-time liquid level L1 of the voltage regulator and the real-time time t1 for calculating the coolant leakage rate; obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula.

[0059] The present invention also provides a computer device, including a processor, a memory, and a bus, wherein the memory stores a computer program executable by the processor, and when the computer device is running, the processor communicates with the memory via the bus, and the processor executes the computer program to perform the steps of any of the above methods, or any possible implementation of any of the methods.

[0060] The present invention also provides a computer-readable storage medium storing a computer program, which a processor executes to perform the steps of any of the above methods, or any possible implementation of any of the methods.

[0061] The technical solution of this invention has the following beneficial effects: S1. Monitor and determine whether the primary loop meets the initial conditions for starting the coolant leakage rate calculation; if yes, execute step S2; if no, continue to monitor and determine whether the primary loop meets the initial conditions for starting the coolant leakage rate calculation until the initial conditions for starting the coolant leakage rate calculation are met; S2. Obtain the liquid level and initial liquid level of the primary loop pressurizer, and start calculating the coolant leakage rate to obtain the calculation result of the coolant leakage rate; and determine whether the calculation result of the coolant leakage rate exceeds the preset leakage rate limit; if yes, issue an accident procedure warning message; thereby realizing self-diagnosis, automatic calculation and judgment of the primary loop coolant leakage rate calculation entry and initial conditions, reducing the risk of human error, improving accident handling efficiency and nuclear power plant safety. Attached Figure Description

[0062] To more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below only show some embodiments of the present invention, and therefore should not be regarded as a limitation on the scope of protection. For those skilled in the art, other related drawings can be obtained based on these drawings without creative effort.

[0063] Figure 1 This is a flowchart illustrating an embodiment of the automatic diagnosis method for primary loop leakage rate in nuclear power plants provided by the present invention. Detailed Implementation

[0064] To make the objectives and advantages of the embodiments of the present invention more readily understood, 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 a part of the embodiments of the present invention, and not all of them. The detailed description of the embodiments of the present invention in the accompanying drawings is not intended to limit the scope of protection claimed by the present invention, but merely to illustrate selected embodiments of the present invention. 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.

[0065] It should be noted that similar labels and letters in the following figures indicate similar items. Therefore, once an item is defined in one figure, it does not need to be further defined and explained in subsequent figures.

[0066] To provide a clearer understanding of the technical features, objectives, and effects of the present invention, specific embodiments of the present invention will now be described in detail with reference to the accompanying drawings.

[0067] See Figure 1 This is a flowchart illustrating the automatic diagnostic method for primary loop leakage rate in nuclear power plants, specifically including:

[0068] Step S1: Monitor and determine whether the primary circuit meets the initial conditions for calculating the start-up coolant leakage rate; if yes, proceed to step S2; if no, continue to monitor and determine whether the primary circuit meets the initial conditions for calculating the start-up coolant leakage rate until the initial conditions for calculating the start-up coolant leakage rate are met.

[0069] Step S2: Obtain the liquid level and initial liquid level of the primary circuit voltage regulator, and start calculating the coolant leakage rate to obtain the calculation result of the coolant leakage rate; and determine whether the calculation result of the coolant leakage rate exceeds the preset leakage rate limit; if so, issue an accident procedure warning message.

[0070] Specifically, in an embodiment of the present invention, before executing step S1, in order to determine whether it is necessary to calculate the accident operation leakage rate, it is necessary to first determine whether a radioactive alarm signal has occurred. If the determination is yes, it is determined that the accident operation leakage rate needs to be calculated, and step S1 is executed. The radioactive alarm signal can be obtained from the DCS (Digital Instrument & Control System).

[0071] In an embodiment of the present invention, step S1 includes:

[0072] S1-1: Determine whether the core temperature in the primary loop core measurement system exceeds the preset temperature threshold.

[0073] Determine whether the power load of the steam turbine generator exceeds the preset power threshold; when the core temperature exceeds the temperature threshold and / or the power load exceeds the power threshold, execute step S1-2;

[0074] S1-2: Determine that the primary circuit charging and discharging is in an isolated state; the primary circuit sampling pipeline is in an isolated state; and

[0075] When the primary loop boron and water supply system is in manual mode and shut down, it is determined that the primary loop meets the initial conditions for calculating the start-up coolant leakage rate.

[0076] Specifically, when a radioactive alarm signal is detected, it is determined that an accident operation leakage rate calculation is required. Step S1 is executed to determine whether the primary loop meets the initial conditions for calculating the coolant leakage rate. These initial conditions include: the core temperature in the core measurement system exceeding a preset temperature threshold; the power load of the turbine generator exceeding a preset power threshold; the primary loop charging and discharging being isolated; the primary loop sampling pipeline being isolated; and the primary loop boron and water supply system being in manual mode and shut down. Specifically, the boron and water supply system must be in manual mode and shut down to stop normal water replenishment and drainage operations before the leakage rate calculation can be performed.

[0077] Furthermore, the primary loop charging and discharging is controlled by a chemical and volume control system. The pressure regulator's liquid level is adjusted by controlling the primary loop charging and discharging. Therefore, in order to accurately calculate and determine the leakage rate, the entire primary loop must be isolated, with neither water being added nor drained. Similarly, the primary loop sampling line takes water from the primary loop to detect radioactive substances or other impurities in the water, so it needs to be isolated from the primary loop to ensure that no water is released from the primary loop. When the boron and water supply system is in manual mode and shut down, normal water addition and drainage operations must be stopped before leakage rate calculation can be performed to ensure the accuracy of liquid level measurement and leakage rate calculation.

[0078] In an embodiment of the present invention, when it is monitored and determined that a primary loop meets the above initial conditions, step S2 is executed to initiate the coolant leakage rate calculation. Step S2 includes the following steps:

[0079] S2-1: Obtain the initial liquid level L0 of the primary circuit voltage regulator and record the initial time t0 of the start-up calculation;

[0080] S2-2: Obtain the current liquid level L1 at the current time t1 according to the set rules;

[0081] S2-3: Calculate the coolant leakage rate at the current time based on the initial liquid level L0, initial time t0, current time t1, and current liquid level L1.

[0082] Specifically, the coolant leakage rate is calculated by reading the initial liquid level L0 of the primary loop pressurizer from the nuclear power plant's DCS system and recording the initial time t0 of the calculation. The current liquid level L1 at the current time t1 is obtained according to the set rules.

[0083] Furthermore, the setting rule refers to inputting a trigger signal at a set time interval to trigger the acquisition of the current liquid level L1, and recording the trigger time as the current time t1; or automatically reading the current liquid level L1 at a set time interval and recording the reading time as the current time t1. The coolant leakage rate is then calculated according to formula (1) based on the initial liquid level L0, initial time t0, current time t1, and current liquid level L1. Formula (1) is as follows:

[0084] Qleak=3.464*(L0-L1) / ((t1-t0)+0.23) (1)

[0085] Where Qleak is the calculated coolant leakage rate, L0 is the initial liquid level, L1 is the current liquid level, t0 is the initial time, and t1 is the current time.

[0086] In an embodiment of the present invention, step S2 further includes:

[0087] S2-4: Determine whether the current liquid level L1 is greater than the first liquid level limit. If yes, determine that the coolant leakage rate meets the limit requirements. If no, determine whether the current liquid level L1 is less than the second liquid level limit. If yes, calculate the coolant leakage rate. If the current liquid level L1 is between the first and second liquid level limits, set a time delay, obtain the liquid level at the next moment as the current liquid level L1, and then make a judgment.

[0088] Specifically, after calculating the coolant leakage rate, in order to determine and handle the accident trajectory, it is also necessary to determine the relationship between the current liquid level L1 and the liquid level limit based on the calculated coolant leakage rate result, the liquid level change trend, and the calculation time.

[0089] Further, it is first determined whether the current liquid level L1 is less than the initial liquid level L0. If the determination is no, the pressure regulator liquid level rises or remains unchanged, confirming that the coolant leakage rate does not exceed the preset leakage rate limit. If the determination is yes, the pressure regulator liquid level drops, and it is further determined whether the drop in the pressure regulator liquid level exceeds the preset liquid level change limit. Then, it is determined whether the current liquid level L1 is greater than the first liquid level limit. If yes, it is determined that the coolant leakage rate meets the limit requirements; if no, it is further determined whether the obtained current liquid level L1 is less than the first liquid level limit. At this point, if it is determined that the current liquid level L1 is less than the first liquid level limit, the coolant leakage rate is directly calculated; that is, the current liquid level L1 has dropped compared to the initial liquid level L0, and the drop in liquid level exceeds the limit range.

[0090] Furthermore, when it is determined that the current liquid level L1 is between the first liquid level limit and the second liquid level limit, a time delay is set. At the end of the delay, the liquid level at that moment is read and taken as the current liquid level L1, and the moment is recorded as the current time t1. Then, it is determined whether the current liquid level L1 is still between the first liquid level limit and the second liquid level limit. If it is determined to be yes, the coolant leakage rate is determined to meet the limit requirements; that is, although the current liquid level L1 has decreased compared to the initial liquid level L0, the decrease in liquid level is still within the limited range. Preferably, the delay time is set to 20 minutes.

[0091] In an embodiment of the present invention, step S2-2 further includes: when reading the liquid level of the primary circuit regulator, it is necessary to first determine whether the liquid level of the regulator is displayed as a readable normal value; if the liquid level of the regulator is displayed as a readable normal value, it is determined that the source signal is valid, and the liquid level of the primary circuit regulator is recorded as the current liquid level L1; if the liquid level of the regulator is not displayed as a readable normal value, it is determined that the source signal is invalid, and at this time, the primary circuit needs to pause the calculation of the coolant leakage rate. The source signal for initiating the calculation of the coolant leakage rate is the liquid level of the regulator.

[0092] Specifically, when reading the coolant level of the primary circuit regulator, it is determined whether the regulator's level is displayed as a readable, normal value. If the regulator's level is not displayed as a readable, normal value, the source signal is considered invalid, and the primary circuit suspends the calculation of the coolant leakage rate. This indicates a calculation parameter error; after pausing the coolant leakage rate calculation at this point, it can be restarted.

[0093] In an optional embodiment, the coolant leakage rate calculation is restarted, and the liquid level of the primary circuit regulator is read. The initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation recorded in step S2-1 can be kept unchanged. Then, the time interval is set, and the trigger signal is re-inputted to trigger the acquisition of the current liquid level L1, and the trigger time is recorded as the current time t1. Alternatively, the current liquid level L1 is automatically re-read at the set time interval, and the reading time is recorded as the current time t1. The coolant leakage rate is recalculated according to the coolant leakage rate calculation formula, and then steps S2-3 and S2-4 are executed.

[0094] In another optional embodiment, the coolant leakage rate calculation is restarted, the liquid level of the primary circuit regulator is read, step S2-1 can be re-executed, the initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation are re-recorded; the time interval is set again, the trigger signal is re-inputted to trigger the acquisition of the current liquid level L1, and the trigger time is recorded as the current time t1; or, the current liquid level L1 is automatically re-read at the set time interval, and the reading time is recorded as the current time t1; and the coolant leakage rate calculation result is recalculated according to the coolant leakage rate calculation formula, and then steps S2-3 and S2-4 are continued.

[0095] The technical solution of this embodiment monitors and determines whether the primary loop meets the initial conditions for starting the coolant leakage rate calculation; if not, it continues to monitor and determine whether the primary loop meets the initial conditions for starting the coolant leakage rate calculation until the initial conditions for starting the coolant leakage rate calculation are met; if yes, it acquires the liquid level and initial liquid level of the primary loop pressurizer, and starts calculating the coolant leakage rate to obtain the calculation result of the coolant leakage rate; it then determines whether the calculation result of the coolant leakage rate exceeds the preset leakage rate limit; if yes, it issues an accident procedure warning message; thereby realizing self-diagnosis, automatic calculation and judgment of the primary loop coolant leakage rate calculation entry and initial conditions, reducing the risk of human error, improving accident handling efficiency and nuclear power plant safety.

[0096] Those skilled in the art will understand that, in the above-described method of the specific implementation, the order in which each step is written does not imply a strict execution order and does not constitute any limitation on the implementation process. The specific execution order of each step should be determined by its function and possible internal logic.

[0097] This invention also provides an automatic diagnostic system for the primary loop leakage rate of a nuclear power plant, which applies any of the above automatic diagnostic methods and specifically includes:

[0098] The monitoring module is used to monitor and determine whether the primary loop meets the initial conditions for calculating the start-up coolant leakage rate;

[0099] The calculation module is used to read the liquid level of the primary circuit regulator, start the coolant leakage rate calculation, and obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula.

[0100] The early warning module is used to determine whether the calculated result of the coolant leakage rate exceeds the preset leakage rate limit; if so, it issues an accident procedure early warning message.

[0101] In embodiments of the present invention, the monitoring module further includes a first monitoring submodule, a second monitoring submodule, a third monitoring submodule, a fourth monitoring submodule, and a fifth monitoring submodule:

[0102] Furthermore, the first monitoring submodule is used to monitor and determine whether the core temperature in the primary loop core measurement system exceeds a preset temperature threshold; the second monitoring submodule is used to monitor and determine whether the power load of the turbine generator exceeds a preset power threshold; the third monitoring submodule is used to monitor and determine whether the primary loop charging and discharging systems are in an isolated state; the fourth monitoring submodule is used to monitor and determine whether the primary loop sampling pipeline is in an isolated state; and the fifth monitoring submodule is used to monitor and determine whether the primary loop boron and water replenishment system is in a manual state and shut down.

[0103] In embodiments of the present invention, the calculation module further includes a reading submodule and a calculation submodule:

[0104] Furthermore, the reading submodule is used to read the liquid level of the primary circuit regulator, initiate the coolant leakage rate calculation, and record the initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation; the calculation submodule is used to set the delay time, record the real-time liquid level L1 of the regulator and the real-time time t1 of the coolant leakage rate calculation, and obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula, and determine whether the real-time liquid level L1 of the regulator is less than the initial liquid level L0 of the regulator.

[0105] Furthermore, the reading submodule is also used to read the liquid level of the primary circuit regulator and determine whether the liquid level of the regulator is displayed as a readable normal value; the source signal for starting the coolant leakage rate calculation is the liquid level of the regulator; if the liquid level of the regulator is displayed as a readable normal value, it is determined that the source signal is valid, the primary circuit starts the coolant leakage rate calculation, and records the initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation; if the liquid level of the regulator is not displayed as a readable normal value, it is determined that the source signal is invalid, and the primary circuit suspends the coolant leakage rate calculation.

[0106] Furthermore, the calculation submodule also includes a first calculation submodule, a second calculation submodule, a third calculation submodule, and a fourth calculation submodule:

[0107] Furthermore, the first calculation submodule is used to set a delay time for timing, continue to read the liquid level of the primary circuit regulator to obtain the rate of change of the regulator's liquid level, and record the real-time liquid level L1 of the regulator and the real-time time t1 for calculating the coolant leakage rate. According to the coolant leakage rate calculation formula, the calculation result of the coolant leakage rate is obtained. Based on the recorded real-time liquid level L1 and the initial liquid level L0 of the regulator, it is determined whether the real-time liquid level L1 of the regulator is less than the initial liquid level L0 of the regulator. If so, the liquid level of the regulator drops. Based on the obtained rate of change of the regulator's liquid level, it is determined whether the drop in the regulator's liquid level exceeds the preset liquid level change limit. If not, the liquid level of the regulator rises or remains unchanged, confirming that the coolant leakage rate does not exceed the preset leakage rate limit.

[0108] Furthermore, the second calculation submodule is used to determine whether the drop in the liquid level of the regulator exceeds a preset liquid level change limit when it is determined whether the real-time liquid level L1 of the regulator is less than the initial liquid level L0 of the regulator. If yes, step S3 is executed; if no, a delay time is set, and the liquid level of the first-loop regulator is read again during the delay time to obtain the liquid level change rate of the regulator. When the delay time ends, the liquid level drop in the regulator exceeds the preset liquid level change limit based on the obtained liquid level change rate of the regulator.

[0109] Furthermore, the third calculation submodule is used to set a delay time when determining whether the liquid level drop of the pressure regulator exceeds the preset liquid level change limit. During the delay time, the liquid level of the primary circuit pressure regulator is continuously read to obtain the liquid level change rate of the pressure regulator. When the delay time ends, based on the obtained liquid level change rate of the pressure regulator, it is further determined whether the liquid level drop of the pressure regulator exceeds the preset liquid level change limit. If yes, step S3 is executed; if no, it is determined that the coolant leakage rate does not exceed the preset leakage rate limit.

[0110] Furthermore, the fourth calculation submodule is used to read the liquid level of the primary circuit regulator, restart the coolant leakage rate calculation, keep the recorded initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation unchanged; set the timer delay time, re-record the real-time liquid level L1 of the regulator and the real-time time t1 of the coolant leakage rate calculation; and obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula.

[0111] Furthermore, the fourth calculation submodule can also be used to read the liquid level of the primary circuit regulator, restart the coolant leakage rate calculation, and re-record the initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation; set the timer delay time, and re-record the real-time liquid level L1 of the regulator and the real-time time t1 of the coolant leakage rate calculation; and obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula.

[0112] The present invention also provides a computer device, including a processor, a memory, and a bus. The memory stores a computer program executable by the processor. When the computer device is running, the processor communicates with the memory via the bus, and the processor executes the computer program to perform any of the above methods, or any possible implementation of any of the methods.

[0113] The present invention also provides a computer-readable storage medium storing a computer program, which a processor executes to perform the steps of any of the above methods, or any possible implementation of any of the methods.

[0114] Those skilled in the art will understand that the embodiments provided by this invention are merely illustrative. The order in which the steps in the methods of the embodiments are written does not imply a strict execution order and does not constitute any limitation on the implementation process. The order can be adjusted, merged, and deleted according to actual needs. The modules or sub-modules, units, or sub-units in the apparatus of the embodiments can be merged, divided, and deleted according to actual needs. For example, the division of units is merely a logical functional division, and there may be other division methods in actual implementation. For another example, multiple units or components can be combined or integrated into another device, or some features can be ignored or not executed.

[0115] Those skilled in the art will recognize that all or part of the steps of the methods described in the embodiments of this invention can be implemented directly using electronic hardware or a processor-executable computer program, or a combination of both. The computer program can be stored in random access memory (RAM), read-only memory (ROM), main memory, electrically programmable ROM, electrically erasable programmable ROM, CD-ROM, registers, hard disk, removable disk, or any other form of storage medium known in the art.

[0116] It should be noted that 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 should not be used to limit the scope of protection of the present invention. Those skilled in the art can understand that all or part of the processes of implementing the above embodiments, and all equivalent changes and modifications made in accordance with the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. An automatic diagnostic method for primary loop leakage rate in a nuclear power plant, characterized in that, include: S1. Determine whether a radioactive alarm signal has occurred. If the determination is yes, monitor and determine whether the primary circuit meets the initial conditions for calculating the coolant leakage rate. If yes, proceed to step S2; otherwise, continue monitoring and determining whether the first loop meets the initial conditions for calculating the start-up coolant leakage rate until the initial conditions for calculating the start-up coolant leakage rate are met. S2. Obtain the liquid level and initial liquid level of the primary circuit voltage regulator, and start calculating the coolant leakage rate to obtain the calculation result of the coolant leakage rate; and determine whether the calculation result of the coolant leakage rate exceeds the preset leakage rate limit; if so, issue an accident procedure warning message. In step S1, monitoring and determining whether the primary circuit meets the initial conditions for calculating the start-up coolant leakage rate includes: S1-1: Determine whether the temperature of the core in the primary loop core measurement system exceeds a preset temperature threshold. Determine whether the power load of the steam turbine generator exceeds the preset power threshold; When the temperature of the reactor core exceeds the temperature threshold and / or the power load exceeds the power threshold, step S1-2 is executed; S1-2: Determine that the charging and discharging circuit is in an isolated state; The primary sampling pipeline is in an isolated state; and When the primary loop boron and water supply system is in manual mode and shut down, it is determined that the primary loop meets the initial conditions for calculating the coolant leakage rate.

2. The automatic diagnostic method according to claim 1, characterized in that, Step S2 includes the following steps: S2-1: Obtain the initial liquid level L0 of the primary circuit voltage regulator and record the initial time t0 of the start calculation; S2-2: Obtain the current liquid level L1 at the current time t1 according to the set rules; S2-3: Calculate the coolant leakage rate at the current time based on the initial liquid level L0, initial time t0, current time t1, and current liquid level L1.

3. The automatic diagnostic method according to claim 2, characterized in that, In step S2-2, the setting rule includes: inputting a trigger signal at a set time interval to trigger the acquisition of the current liquid level L1, and recording the trigger time as the current time t1; or The current liquid level L1 is automatically read at set time intervals, and the reading time is recorded as the current time t1.

4. The automatic diagnostic method according to claim 2, characterized in that, In steps S2-3, Qleak=3.464 The coolant leakage rate is calculated using (L0-L1) / ((t1-t0)+0.23).

5. The automatic diagnostic method according to claim 2, characterized in that, Step S2 further includes: S2-4: Determine whether the current liquid level L1 is greater than the first liquid level limit. If so, determine that the coolant leakage rate meets the limit requirements. If not, determine whether the current liquid level L1 is less than the second liquid level limit; if so, calculate the coolant leakage rate. If the current liquid level L1 is between the first liquid level limit and the second liquid level limit, a time delay is set, and the liquid level at the next moment is obtained as the current liquid level L1, and then a judgment is made.

6. The automatic diagnostic method according to claim 2, characterized in that, In step S2-2, the liquid level of the primary circuit regulator is read, and it is determined whether the liquid level of the regulator is displayed as a readable normal value. If the liquid level display of the voltage regulator is a readable normal value, it is determined that the source signal is valid, and the liquid level of the first-loop voltage regulator is recorded as the current liquid level L1; If the liquid level of the pressure regulator is not displayed as a readable normal value, it is determined that the source signal is invalid, and the first loop suspends the calculation of the coolant leakage rate.

7. An automatic diagnostic system for primary loop leakage rate in a nuclear power plant, applied to the automatic diagnostic method described in any one of claims 1-6, characterized in that, The automated diagnostic system includes: The monitoring module is used to monitor and determine whether the primary circuit meets the initial conditions for calculating the coolant leakage rate after a radioactive alarm signal is detected. The calculation module is used to read the liquid level of the primary circuit regulator, start the coolant leakage rate calculation, and obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula. The early warning module is used to determine whether the calculated result of the coolant leakage rate exceeds the preset leakage rate limit; if so, it issues an accident procedure early warning message. The monitoring module includes: The first monitoring submodule is used to monitor and determine whether the temperature of the core in the primary loop core measurement system exceeds a preset temperature threshold. The second monitoring submodule is used to monitor and determine whether the power load of the steam turbine generator exceeds the preset power threshold. The third monitoring submodule is used to monitor and determine whether the charging and discharging of the primary circuit is in an isolated state. The fourth monitoring submodule is used to monitor and determine whether the primary loop sampling pipeline is in an isolated state; The fifth monitoring submodule is used to monitor and determine whether the primary loop boron and water supply system is in manual mode and shut down.

8. The automatic diagnostic system according to claim 7, characterized in that, The computing module also includes: The reading submodule is used to read the liquid level of the primary circuit regulator, start the coolant leakage rate calculation, and record the initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation. The calculation submodule is used to set the delay time, record the real-time liquid level L1 of the pressure regulator and the real-time time t1 of the coolant leakage rate calculation, obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula, and determine whether the real-time liquid level L1 of the pressure regulator is less than the initial liquid level L0 of the pressure regulator.

9. The automatic diagnostic system according to claim 8, characterized in that, The reading submodule is also used to read the liquid level of the primary circuit regulator and determine whether the liquid level of the regulator is displayed as a readable normal value; the source signal for initiating the coolant leakage rate calculation is the liquid level of the regulator; If the liquid level display of the pressure regulator is a readable normal value, it is determined that the source signal is valid. The first loop starts the coolant leakage rate calculation and records the initial liquid level L0 of the pressure regulator and the initial time t0 of the coolant leakage rate calculation. If the liquid level of the pressure regulator is not displayed as a readable normal value, it is determined that the source signal is invalid, and the first loop suspends the calculation of the coolant leakage rate.

10. The automatic diagnostic system according to claim 9, characterized in that, The computation submodule also includes: The first calculation submodule is used to set a time delay, continue to read the liquid level of the primary circuit regulator to obtain the rate of change of the liquid level of the regulator, and record the real-time liquid level L1 of the regulator and the real-time time t1 of the coolant leakage rate calculation. According to the coolant leakage rate calculation formula, the calculation result of the coolant leakage rate is obtained. Based on the recorded real-time liquid level L1 and the initial liquid level L0 of the voltage regulator, determine whether the real-time liquid level L1 of the voltage regulator is less than the initial liquid level L0 of the voltage regulator. If so, the liquid level of the pressure regulator drops, and based on the obtained rate of change of the liquid level of the pressure regulator, it is determined whether the drop in the liquid level of the pressure regulator exceeds the preset liquid level change limit; if not, the liquid level of the pressure regulator rises or remains unchanged, and it is determined that the coolant leakage rate does not exceed the preset leakage rate limit. The second calculation submodule is used to determine whether the drop in the liquid level of the regulator exceeds a preset liquid level change limit based on the obtained rate of change of the liquid level of the regulator when it is determined that the real-time liquid level L1 of the regulator is less than the initial liquid level L0 of the regulator. If yes, proceed to step S3; if no, set a delay time, and during the delay time, continue to read the liquid level of the primary circuit regulator to obtain the rate of change of the liquid level of the regulator; when the delay time ends, determine whether the drop in the liquid level of the regulator exceeds the preset liquid level change limit based on the obtained rate of change of the liquid level of the regulator. The third calculation submodule is used to set a delay time when determining whether the drop in the liquid level of the regulator exceeds the preset liquid level change limit. During the delay time, the liquid level of the primary circuit regulator is continued to be read to obtain the rate of change of the liquid level of the regulator. When the delay time ends, based on the obtained rate of change of the liquid level of the regulator, it is further determined whether the drop in the liquid level of the regulator exceeds the preset liquid level change limit. If yes, proceed to step S3; if no, determine that the coolant leakage rate does not exceed the preset leakage rate limit. The fourth calculation submodule is used to read the liquid level of the primary circuit regulator, restart the coolant leakage rate calculation, and keep the recorded initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation unchanged. Set a timeout period and re-record the real-time liquid level L1 of the voltage regulator and the real-time time t1 for calculating the coolant leakage rate; obtain the calculated result of the coolant leakage rate according to the coolant leakage rate calculation formula; or Used to read the liquid level of the primary circuit regulator, restart the coolant leakage rate calculation, and re-record the initial liquid level L0 of the regulator and the initial time t0 of the coolant leakage rate calculation; Set a timeout period and re-record the real-time liquid level L1 of the voltage regulator and the real-time time t1 for calculating the coolant leakage rate; obtain the calculation result of the coolant leakage rate according to the coolant leakage rate calculation formula.

Images