Method, system, device and storage medium for diagnosing breach position of chemical containment system
By automatically calculating liquid level changes and the comparison of the shaft seal net injection flow, the breaking position of the nuclear power plant capacity system is quickly judged, which solves the problem of manual judgment time, reduces coolant emissions, and improves the efficiency and safety of accident handling .
Patent Information
- Application Number
- CN202211246431.7
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- Filing Date
- 2022-10-12
- Publication Date
- 2024-12-13
- Estimated Expiration
- 2042-10-12
AI Technical Summary
In nuclear power plants, when there is a small breakage accident, it takes a long time to manually calculate and determine whether the breakage position is located on the chemical capacity system, which affects the accident handling and may lead to excessive cooling agent emissions in the first circuit.
The automatic diagnosis method of the breaking position of the nuclear power plant capacity system is adopted. By obtaining the liquid level change value and the shaft sealing net injection flow of the voltage regulator in the preset time period, comparing the liquid level change value with the set value, and outputting the breaking position Diagnostic information, realizes automatic calculation and rapid judgment.
It realizes the rapid determination of the location of the break after the break accident, timely handling the accident, reduces the discharge of one-loop coolant, and improves the efficiency and safety of accident handling.
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Figure CN115597010B_ABST
Abstract
Description
Technical Field
[0001] The present invention relates to the technical field of nuclear power plant control rooms, and in particular to a method, system, device and storage medium for diagnosing the breach position of a chemical containment system. Background Art
[0002] Among the many systems in a nuclear power plant, the primary circuit system is an important barrier to ensure nuclear safety. In order to prevent the leakage of radioactive materials in the primary circuit, a lot of analysis is carried out during the design process of the nuclear power plant and corresponding regulations are formulated.
[0003] Accidents with small breaches in the primary circuit system are controlled through accident operation procedures. However, in the actual execution of the procedures, operators need to perform manual calculations and combine static graphics to determine whether the breach is located on the chemical containment system of the primary circuit auxiliary system. The entire judgment process takes a long time, which is not conducive to accident handling and may lead to more discharge of primary circuit coolant. How to quickly and effectively determine whether the breach is located on the chemical containment system has become a concern for nuclear power plant designers. Summary of the invention
[0004] The technical problem to be solved by the present invention is to provide a method, system, device and storage medium for diagnosing the breach position of a chemical containment system.
[0005] The technical solution adopted by the present invention to solve the technical problem is: constructing a method for automatically diagnosing the breach position of a chemical containment system of a nuclear power plant, comprising the following steps:
[0006] S1: After isolating the upper filling pipe and the lower discharge pipe in the chemical volume system, obtaining a first liquid level change value of a pressure stabilizer connected to the chemical volume system within a first preset time period;
[0007] S2: obtaining a shaft seal net injection flow rate of the chemical volume system within the first preset time period, and obtaining a liquid level change setting value of the pressurizer according to the shaft seal net injection flow rate;
[0008] S3: comparing the first liquid level change value with the liquid level change set value, and obtaining a comparison result;
[0009] S4: Outputting breach position diagnosis information according to the comparison result.
[0010] Preferably, in step S1, obtaining the first liquid level change value comprises the following steps:
[0011] S11: obtaining a second liquid level change value of the voltage regulator within a second preset time period; the length of the second preset time period is shorter than the length of the first preset time period;
[0012] S12: Obtaining the first liquid level change value according to the first preset time period, the second preset time period and the second liquid level change value.
[0013] Preferably, in step S12, the first liquid level change value is calculated according to formula a, and formula a is:
[0014]
[0015] Among them, L T represents the first liquid level change value, L 10 represents the second liquid level change value, T represents the first preset time period, t 10 Represents the second preset time period.
[0016] Preferably, in step S2, the liquid level change set value is calculated according to formula b, which is:
[0017]
[0018] Wherein, △L represents the set value of the liquid level change, Q 10 represents the net injection flow of the shaft seal, T represents the first preset time period, and S represents the cross-sectional area of the stabilizer.
[0019] Preferably, obtaining the net shaft seal injection flow of the chemical volume system within the first preset time period comprises the following steps:
[0020] S21: obtaining the injection flow rate of the main pump shaft seal of the chemical volume system within the first preset time period;
[0021] S23: obtaining the shaft seal reflux flow rate of the main pump of the chemical volume system within the first preset time period;
[0022] S22: Obtaining the shaft seal net injection flow rate according to the main pump shaft seal injection flow rate and the main pump shaft seal return flow rate.
[0023] Preferably, the comparison result includes:
[0024] The first liquid level change value is greater than or equal to the liquid level change set value;
[0025] Or, the first liquid level change value is less than the liquid level change set value;
[0026] In step S4, the following steps are included:
[0027] When the first liquid level change value is greater than or equal to the liquid level change set value, outputting diagnostic information that the breach position is located within the chemical volume system;
[0028] When the first liquid level change value is less than the liquid level change set value, the diagnostic information that the breach position is outside the chemical volume system is output.
[0029] The present invention also constructs a nuclear power plant chemical containment system breach position automatic diagnosis system, comprising:
[0030] A first execution module is used to obtain a first liquid level change value of a pressure regulator connected to the chemical volume system within a first preset time period after isolating an upper filling pipe and a lower discharge pipe in the chemical volume system;
[0031] A second execution module is used to obtain a shaft seal net injection flow rate of the chemical volume system within the first preset time period, and obtain a liquid level change setting value of the pressurizer according to the shaft seal net injection flow rate;
[0032] A comparison module, used for comparing the first liquid level change value with the liquid level change set value and obtaining a comparison result;
[0033] The output module is used to output the breach position diagnosis information according to the comparison result.
[0034] Preferably, the first execution module includes:
[0035] A first acquisition unit is used to acquire a second liquid level change value of the voltage stabilizer within a second preset time period; the length of the second preset time period is shorter than the length of the first preset time period;
[0036] The first calculation unit is used to obtain the first liquid level change value according to the first preset time period, the second preset time period and the second liquid level change value.
[0037] Preferably, the first operation unit calculates the first liquid level change value according to formula a, and the formula a is:
[0038]
[0039] Among them, L T represents the first liquid level change value, L 10 represents the second liquid level change value, T represents the first preset time period, t 10 Represents the second preset time period.
[0040] Preferably, the second execution module calculates the liquid level change setting value according to formula b, and the formula b is:
[0041]
[0042] Wherein, △L represents the set value of the liquid level change, Q 10represents the net injection flow of the shaft seal, T represents the first preset time period, and S represents the cross-sectional area of the stabilizer.
[0043] Preferably, the second execution module includes:
[0044] A second acquisition unit, used for acquiring the injection flow of the main pump shaft seal of the chemical volume system within the first preset time period;
[0045] A third acquisition unit is used to acquire the shaft seal reflux flow of the main pump of the chemical volume system within the first preset time period;
[0046] The second calculation unit is used to obtain the shaft seal net injection flow rate according to the main pump shaft seal injection flow rate and the main pump shaft seal return flow rate.
[0047] Preferably, the comparison result includes:
[0048] The first liquid level change value is greater than or equal to the liquid level change set value;
[0049] Or, the first liquid level change value is less than the liquid level change set value;
[0050] The output module outputs the diagnostic information that the breach is located within the chemical volume system when the first liquid level change value is greater than or equal to the liquid level change set value;
[0051] When the first liquid level change value is less than the liquid level change set value, the output module outputs diagnostic information that the breach position is outside the chemical volume system.
[0052] The present invention also constructs an automatic diagnosis device for the breach position of a containment system of a nuclear power plant, comprising a processor and a memory storing a computer program, and the processor implements the steps of the automatic diagnosis method for the breach position of a containment system of a nuclear power plant when executing the computer program.
[0053] The present invention also constructs a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, the steps of the above-mentioned method for automatically diagnosing the breach position of the chemical containment system of a nuclear power plant are implemented.
[0054] The implementation of the present invention has the following beneficial effects: the automatic diagnosis method for the breach position of the chemical containment system of a nuclear power plant can realize automatic calculation, and quickly and effectively determine whether the breach position is located on the chemical containment system after a breach accident occurs, so that the accident can be handled in time and the discharge of the primary circuit coolant can be reduced. BRIEF DESCRIPTION OF THE DRAWINGS
[0055] The present invention will be further described below with reference to the accompanying drawings and embodiments, in which:
[0056] Figure 1 is a flow chart of some embodiments of the method for automatically diagnosing the breach position of the chemical containment system of a nuclear power plant according to the present invention;
[0057] Figure 2 It is a connection relationship diagram of the primary loop system and the chemical volume system of the nuclear power plant of the present invention;
[0058] Figure 3 It is a flow chart of another embodiment of the method for automatically diagnosing the breach position of the chemical containment system of a nuclear power plant according to the present invention. DETAILED DESCRIPTION
[0059] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, specific embodiments of the present invention are now described in detail with reference to the accompanying drawings.
[0060] It should be noted that the flowcharts shown in the accompanying drawings are only exemplary and do not necessarily include all the contents and operations / steps, nor do they have to be executed in the order described. For example, some operations / steps can be decomposed, while some operations / steps can be combined or partially combined, so the actual execution order may change according to actual conditions.
[0061] The block diagrams shown in the accompanying drawings are merely functional entities and do not necessarily correspond to physically independent entities. That is, these functional entities may be implemented in software form, or in one or more hardware modules or integrated circuits, or in different networks and / or processor devices and / or microcontroller devices.
[0062] See also Figure 1 The present invention constructs an automatic diagnosis method for the breach position of a chemical containment system, which can be applied to nuclear power plants. The diagnosis method can realize automatic calculation and quickly and effectively determine whether the breach position is located on the chemical containment system 2 after a breach accident occurs, so that the accident can be handled in time and the discharge of primary circuit coolant can be reduced.
[0063] like Figure 1 and Figure 3 As shown, in some embodiments, the method for automatically diagnosing the breach position of a chemical volume system includes the following steps:
[0064] S1: After isolating the upper filling pipe 211 and the lower discharge pipe 221 in the chemical volume system 2, obtaining a first liquid level change value of the pressurizer 13 connected to the chemical volume system 2 within a first preset time period;
[0065] It is understandable that, generally, see Figure 2The primary loop system 1 includes a main pump 11, a core 12, a pressurizer 13, a steam generator 14, and a main loop 15 that connects the main pump 11, the core 12, the pressurizer 13, and the steam generator 14 in a diversion manner. As a major auxiliary system of the primary loop system 1, the chemical volume system 2 has a volume control function, which can maintain the water level of the pressurizer 13 through the up-filling and down-discharging functions, thereby maintaining the primary loop water volume.
[0066] Generally, see Figure 2 The chemical volume system 2 includes an upper charging pipeline, a lower discharge pipeline and a shaft sealing pipeline. The upper charging pipeline and the lower discharge pipeline are respectively connected to the main circuit 15 located on both sides of the main pump 11, and the shaft sealing pipeline is connected to the main pump shaft seal of the main pump 11. Among them, the upper charging pipeline includes an upper charging pipeline 211, an upper charging pump 212 and an upper charging valve 213, the lower discharge pipeline includes a lower discharge pipeline 221 and a lower discharge valve 222, and the shaft sealing pipeline includes a shaft seal injection pipeline 231 and a shaft seal return pipeline 232. The upper charging pipeline 211 and the lower discharge pipeline 221 are respectively connected to the main circuit 15 located on both sides of the main pump 11, the upper charging valve 213 is used to open and close the upper charging pipeline 211, and the lower discharge valve 222 is used to open and close the lower discharge pipeline 221. The chemical volume system 2 can lead out the lower discharge flow of the primary circuit system 1 through the lower discharge pipeline 221, and can also return the upper charging flow to the primary circuit system 1 through the upper charging pipeline 211 through the upper charging pump 212. The shaft seal injection pipe 231 and the shaft seal return pipe 232 are respectively connected to the main pump shaft seal of the main pump 11. The specific connection relationship of the chemical volume system 2 can be referred to Figure 2 , I will not go into details here.
[0067] After a breach accident occurs, it is necessary to first isolate the upper filling and lower discharge functions in the chemical volume system 2, and only retain the shaft seal injection and shaft seal reflux functions, in order to ensure that the water inlet source of a circuit is unique. Among them, isolating the upper filling and lower discharge functions means isolating the upper filling pipe 211 and the lower discharge pipe 221. The isolation method can be to close (cut off) the upper filling pipe 211 and the lower discharge pipe 221 by controlling the upper filling valve 213 and the lower discharge valve 222.
[0068] After the upper charging and lower discharging functions in the chemical volume system 2 are isolated, the automatic diagnosis method for the breach position of the present invention is started, that is, step S1 is executed.
[0069] In some embodiments, the method of obtaining the first liquid level change value may include:
[0070] At a first time point, the liquid level of the pressurizer 13 is collected and recorded as a first liquid level value;
[0071] At a second time point, the liquid level of the pressurizer 13 is collected and recorded as a second liquid level value;
[0072] A first liquid level change value is obtained according to the first liquid level value and the second liquid level value.
[0073] The first preset time period is the time length from the first time point (initial time point) to the second time point (end time point), and the first liquid level change value is the difference between the second liquid level value and the first liquid level value. In some embodiments, a liquid level meter may be provided in the stabilizer 13, and the current liquid level of the stabilizer 13 may be collected by the liquid level meter. Optionally, the first preset time period may be 30-60 minutes.
[0074] S2: Obtaining the net shaft seal injection flow of the chemical volume system 2 within a first preset time period, and obtaining a liquid level change setting value of the pressurizer 13 according to the net shaft seal injection flow;
[0075] It can be understood that the net shaft seal injection flow refers to the difference between the main pump shaft seal injection flow introduced into the main pump shaft seal from the shaft seal injection pipe 231 of the chemical volume system 2 and the main pump shaft seal return flow returned to the chemical volume system 2 through the shaft seal return pipe 232 of the chemical volume system 2.
[0076] In some embodiments, obtaining the net shaft seal injection flow of the chemical volume system 2 within the first preset time period includes:
[0077] Obtaining the main pump shaft seal injection flow rate introduced from the shaft seal injection pipeline 231 of the chemical volume system 2 to the main pump shaft seal within the first preset time period;
[0078] Obtaining the main pump shaft seal reflux flow rate that flows back to the chemical volume system 2 through the shaft seal reflux pipeline 232 of the chemical volume system 2 within the first preset time period;
[0079] The net injection flow of the shaft seal is calculated based on the injection flow of the main pump shaft seal and the return flow of the main pump shaft seal.
[0080] Optionally, the main pump shaft seal injection flow and the main pump shaft seal return flow can be extracted by relying on the DCS system.
[0081] In addition, the liquid level change setting value is the liquid level change value of the regulator 13 corresponding to the shaft seal net injection flow rate in the same time period. Different shaft seal net injection flows correspond to different liquid level change setting values, and all liquid level change setting values can form a linear curve.
[0082] In some embodiments, the liquid level change set value is calculated according to the following relationship (b), which is specifically:
[0083] (b)
[0084] Among them, △L represents the set value of liquid level change, Q 10 represents the net injection flow of the shaft seal, T represents the first preset time period, and S represents the cross-sectional area of the stabilizer 13.
[0085] S3: Compare the first liquid level change value and the liquid level change set value, and obtain a comparison result;
[0086] It can be understood that comparing the first liquid level change value and the liquid level change setting value is to compare the numerical values between the first liquid level change value and the liquid level change setting value. The comparison result may include one of the following: the first liquid level change value is greater than the liquid level change setting value, the first liquid level change value is less than the liquid level change setting value, and the first liquid level change value is equal to the liquid level change setting value.
[0087] S4: Outputting the breach location diagnosis information according to the comparison result.
[0088] It can be understood that when the breach is located in the chemical volume system 2, after isolating the upper filling pipe 211 and the lower discharge pipe 221 of the chemical volume system, the water in the primary circuit system 1 will not continue to leak, and the shaft seal injection water can continue to inject water into the primary circuit system 1, causing the liquid level of the primary circuit system 1 (stabilizer 13) to rise, which is greater than the liquid level change set value (when the shaft seal injection water is not injected, it is equal to).
[0089] When the breach is outside the chemical volume system 2, after isolating the upper filling pipe 211 and the lower discharge pipe 221 of the chemical volume system, the water in the primary circuit system 1 will continue to leak, causing the liquid level of the primary circuit system 1 (pressure regulator 13) to not rise to the liquid level change set value, that is, less than the liquid level change set value. Among them, when it is determined that the breach is outside the chemical volume system 2, it generally means that the breach is on the primary circuit system 1.
[0090] In other words, when the comparison result is that the first liquid level change value is greater than or equal to the liquid level change set value, the output diagnostic information is that the rupture position is inside the chemical volume system 2; and when the comparison result is that the first liquid level change value is less than the liquid level change set value, the output diagnostic information is that the rupture position is outside the chemical volume system 2.
[0091] In some embodiments, the method for automatically diagnosing the breach location of the chemical containment system of a nuclear power plant further includes displaying diagnostic information indicating that the breach location is located inside the chemical containment system 2 or outside the chemical containment system 2 .
[0092] See also Figure 3 As shown, in other embodiments of the method for automatic diagnosis of the breach position of the chemical containment system of a nuclear power plant, since the waiting time required to obtain the first liquid level change value is still relatively long (that is, the first preset time period is too long), it is not conducive to the timeliness of accident handling; in order to shorten the time to obtain the first liquid level change value, a normalized method is used to calculate the first liquid level change value, thereby further shortening the time required for determining the breach position.
[0093] In this embodiment, obtaining a first liquid level change value of a voltage regulator 13 connected to the chemical volume system 2 within a first preset time period includes the following steps:
[0094] S11: obtaining a second liquid level change value of the voltage stabilizer 13 within a second preset time period; the length of the second preset time period is less than the length of the first preset time period;
[0095] S12: Obtaining a first liquid level change value according to the first preset time period, the second preset time period and the second liquid level change value.
[0096] It can be understood that in step S11, obtaining the second liquid level change value of the voltage regulator 13 within the second preset time period may include the following steps:
[0097] At a third time point, the liquid level of the pressurizer 13 is collected and recorded as a third liquid level value;
[0098] At a fourth time point, the liquid level of the voltage regulator 13 is collected and recorded as a fourth liquid level value;
[0099] A second liquid level change value is obtained according to the third liquid level value and the fourth liquid level value.
[0100] The second preset time period is the time length from the third time point to the fourth time point, and the second liquid level change value is the difference between the third liquid level value and the fourth liquid level value. In some embodiments, a liquid level meter may be provided in the voltage stabilizer 13, and the current liquid level of the voltage stabilizer 13 may be collected by the liquid level meter. Optionally, the second preset time period may be 10 to 15 minutes, which is less than the time length of the first preset time period.
[0101] In step S12, the first liquid level change value is calculated according to formula (a), which is:
[0102] (a)
[0103] Among them, L T Represents the first liquid level change value, L 10 represents the second liquid level change value, T represents the first preset time period, t 10 Represents the second preset time period.
[0104] It can be understood that steps S11-S12 obtain the liquid level change value of the regulator 13 in a relatively short period of time, and calculate it in a normalized manner to estimate the liquid level change value of the regulator 13 in a relatively long period of time, thereby shortening the time required to obtain the first liquid level change value.
[0105] In summary, the automatic diagnosis method for the breach location of the chemical containment system of a nuclear power plant of the present invention realizes the location judgment of a small breach in the primary circuit of a nuclear power plant by utilizing mechanisms such as automatic calculation logic and dynamic judgment, thereby ensuring the timeliness of accident handling, reducing the workload of operators in executing accident procedures, and reducing the discharge of primary circuit coolant to the outside.
[0106] The present invention also constructs an automatic diagnosis system for the breach position of a chemical volume system, which in some embodiments may include:
[0107] A first execution module is used to obtain a first liquid level change value of a pressure regulator 13 connected to the chemical volume system 2 within a first preset time period after isolating an upper filling pipe 211 and a lower discharge pipe 221 in the chemical volume system 2;
[0108] A second execution module is used to obtain the net shaft seal injection flow of the chemical volume system 2 within a first preset time period, and obtain a liquid level change setting value of the stabilizer 13 according to the net shaft seal injection flow;
[0109] A comparison module, used for comparing the first liquid level change value and the liquid level change set value, and obtaining a comparison result;
[0110] The output module is used to output the breach location diagnosis information according to the comparison result.
[0111] In some embodiments, the first execution module may include:
[0112] A first collecting unit, used to collect the liquid level of the stabilizer 13 at a first time point and record it as a first liquid level value;
[0113] A second collecting unit, used to collect the liquid level of the stabilizer 13 at a second time point and record it as a second liquid level value;
[0114] The first calculation unit is used to obtain a first liquid level change value according to the first liquid level value and the second liquid level value.
[0115] In some embodiments, the second execution module calculates the liquid level change set value according to formula (b), and formula (b) is:
[0116] (b)
[0117] Among them, △L represents the set value of liquid level change, Q 10 represents the net injection flow of the shaft seal, T represents the first preset time period, and S represents the cross-sectional area of the stabilizer 13.
[0118] In some embodiments, the second execution module includes:
[0119] A second acquisition unit is used to acquire the injection flow rate of the main pump shaft seal of the chemical volume system 2 within a first preset time period;
[0120] A third acquisition unit is used to acquire the shaft seal reflux flow rate of the main pump of the chemical volume system 2 within a first preset time period;
[0121] The second calculation unit is used to obtain the net injection flow of the shaft seal according to the injection flow of the main pump shaft seal and the reflux flow of the main pump shaft seal.
[0122] In some embodiments, the comparison result obtained by the comparison module may include one of the first liquid level change value being greater than the liquid level change set value, the first liquid level change value being less than the liquid level change set value, and the first liquid level change value being equal to the liquid level change set value.
[0123] In some embodiments, after receiving the comparison result output by the comparison module, the output module outputs the rupture position diagnostic information according to the comparison result. When the comparison result is that the first liquid level change value is greater than or equal to the liquid level change setting value, the output module outputs the diagnostic information that the rupture position is located inside the chemical volume system 2; in addition, when the comparison result is that the first liquid level change value is less than the liquid level change setting value, the output module outputs the diagnostic information that the rupture position is outside the chemical volume system 2. It can be understood that when it is determined that the rupture position is outside the chemical volume system 2, it generally means that the rupture position is on the primary circuit system 1.
[0124] In some embodiments, the automatic diagnosis system for breach location of a chemical containment system further includes a display module, and the display module is used to display the breach location diagnosis information output by the output module.
[0125] In other embodiments of the automatic diagnosis system for breach locations of chemical contention systems, another first execution module is used to replace the above-mentioned first execution module, and other modules (second execution module, comparison module and output module) are the same.
[0126] In this embodiment, the other first execution module may include:
[0127] The first acquisition unit is used to acquire a second liquid level change value of the voltage stabilizer 13 within a second preset time period; the time length of the second preset time period is less than the time length of the first preset time period;
[0128] The first operation unit is used to obtain a first liquid level change value according to a first preset time period, a second preset time period and a second liquid level change value.
[0129] Preferably, the first acquiring unit may include:
[0130] A third collecting unit, used to collect the liquid level of the stabilizer 13 at a third time point and record it as a third liquid level value;
[0131] A fourth collecting unit, used for collecting the liquid level of the pressurizer 13 at a fourth time point and recording it as a fourth liquid level value;
[0132] The third calculation unit is used to obtain a second liquid level change value according to the third liquid level value and the fourth liquid level value.
[0133] Preferably, the first operation unit calculates the first liquid level change value according to formula (a), and formula (a) is:
[0134] (a)
[0135] Among them, L T Represents the first liquid level change value, L 10 represents the second liquid level change value, T represents the first preset time period, t 10 Represents the second preset time period.
[0136] In addition, the present invention also constructs an automatic diagnosis device for the breach position of the containment system of a nuclear power plant, including a processor and a memory storing a computer program, and the processor implements the steps of the above-mentioned automatic diagnosis method for the breach position of the containment system of a nuclear power plant when executing the computer program.
[0137] The present invention also constructs a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, the steps of the above-mentioned method for automatically diagnosing the breach position of the chemical containment system of a nuclear power plant are implemented.
[0138] It can be understood that the above embodiments only express the preferred implementation modes of the present invention, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the present invention. It should be pointed out that, for ordinary technicians in this field, the above technical features can be freely combined without departing from the concept of the present invention, and several deformations and improvements can be made, which all belong to the protection scope of the present invention. Therefore, all equivalent changes and modifications made to the scope of the claims of the present invention should belong to the coverage of the claims of the present invention.
Claims
1. A method for automatically diagnosing the breach position of a chemical containment system in a nuclear power plant, characterized in that: The following steps are involved: S1: After isolating the upper filling pipe and the lower discharge pipe in the chemical volume system, obtaining a first liquid level change value of a pressure stabilizer connected to the chemical volume system within a first preset time period; Wherein, obtaining the first liquid level change value comprises the following steps: S11: obtaining a second liquid level change value of the voltage regulator within a second preset time period; the length of the second preset time period is shorter than the length of the first preset time period; S12: Obtain the first liquid level change value according to the first preset time period, the second preset time period and the second liquid level change value; the first liquid level change value is calculated according to formula a, and the formula a is: Among them, L T represents the first liquid level change value, L 10 represents the second liquid level change value, T represents the first preset time period, t 10 represents the second preset time period; S2: obtaining a shaft seal net injection flow rate of the chemical volume system within the first preset time period, and obtaining a liquid level change setting value of the pressurizer according to the shaft seal net injection flow rate; S3: comparing the first liquid level change value with the liquid level change set value, and obtaining a comparison result; S4: Outputting breach position diagnosis information according to the comparison result.
2. The method for automatically diagnosing the breach position of the chemical containment system of a nuclear power plant according to claim 1, characterized in that: In step S2, the liquid level change set value is calculated according to formula b, which is: Wherein, △L represents the set value of the liquid level change, Q 10 represents the net injection flow of the shaft seal, T represents the first preset time period, and S represents the cross-sectional area of the stabilizer.
3. The method for automatically diagnosing the breach position of the chemical containment system of a nuclear power plant according to claim 1, characterized in that: The step of obtaining the net shaft seal injection flow of the chemical volume system within the first preset time period comprises the following steps: S21: obtaining the injection flow rate of the main pump shaft seal of the chemical volume system within the first preset time period; S23: obtaining the shaft seal reflux flow rate of the main pump of the chemical volume system within the first preset time period; S22: Obtaining the shaft seal net injection flow rate according to the main pump shaft seal injection flow rate and the main pump shaft seal return flow rate.
4. The method for automatically diagnosing the breach position of the chemical containment system of a nuclear power plant according to claim 1, characterized in that: The comparison results include: The first liquid level change value is greater than or equal to the liquid level change set value; Or, the first liquid level change value is less than the liquid level change set value; In step S4, the following steps are included: When the first liquid level change value is greater than or equal to the liquid level change set value, outputting diagnostic information that the breach position is located within the chemical volume system; When the first liquid level change value is less than the liquid level change set value, the diagnostic information that the breach position is outside the chemical volume system is output.
5. An automatic diagnosis system for the breach position of the chemical containment system of a nuclear power plant, characterized in that: include: The first execution module is used to obtain a first liquid level change value of a pressure regulator connected to the chemical volume system within a first preset time period after isolating an upper filling pipe and a lower discharge pipe in the chemical volume system; wherein the first execution module includes: A first acquisition unit is used to acquire a second liquid level change value of the voltage stabilizer within a second preset time period; the length of the second preset time period is shorter than the length of the first preset time period; A first operation unit is used to obtain the first liquid level change value according to the first preset time period, the second preset time period and the second liquid level change value; the first operation unit calculates the first liquid level change value according to formula a, and the formula a is: Among them, L T represents the first liquid level change value, L 10 represents the second liquid level change value, T represents the first preset time period, t 10 represents the second preset time period; A second execution module is used to obtain a shaft seal net injection flow rate of the chemical volume system within the first preset time period, and obtain a liquid level change setting value of the pressurizer according to the shaft seal net injection flow rate; A comparison module, used for comparing the first liquid level change value with the liquid level change set value and obtaining a comparison result; The output module is used to output the breach position diagnosis information according to the comparison result.
6. The automatic diagnosis system for breach position of chemical containment system of nuclear power plant according to claim 5, characterized in that: The second execution module calculates the liquid level change setting value according to formula b, and the formula b is: Wherein, △L represents the set value of the liquid level change, Q 10 represents the net injection flow of the shaft seal, T represents the first preset time period, and S represents the cross-sectional area of the stabilizer.
7. The automatic diagnosis system for breach position of chemical containment system of nuclear power plant according to claim 5, characterized in that: The second execution module includes: A second acquisition unit, used for acquiring the injection flow of the main pump shaft seal of the chemical volume system within the first preset time period; A third acquisition unit is used to acquire the shaft seal reflux flow of the main pump of the chemical volume system within the first preset time period; The second calculation unit is used to obtain the shaft seal net injection flow rate according to the main pump shaft seal injection flow rate and the main pump shaft seal return flow rate.
8. The automatic diagnosis system for breach position of chemical containment system of nuclear power plant according to claim 5, characterized in that: The comparison results include: The first liquid level change value is greater than or equal to the liquid level change set value; Or, the first liquid level change value is less than the liquid level change set value; The output module outputs the diagnostic information that the breach is located within the chemical volume system when the first liquid level change value is greater than or equal to the liquid level change set value; When the first liquid level change value is less than the liquid level change set value, the output module outputs diagnostic information that the breach position is outside the chemical volume system.
9. An automatic diagnosis device for the breach position of a chemical containment system in a nuclear power plant, characterized in that: The invention comprises a processor and a memory storing a computer program, and the processor implements the steps of the method for automatically diagnosing the breach position of the chemical containment system of a nuclear power plant as described in any one of claims 1 to 4 when executing the computer program.
10. A computer-readable storage medium, characterized in that: The computer-readable storage medium stores a computer program, and when the computer program is executed by a processor, the steps of the method for automatically diagnosing the breach location of the chemical containment system of a nuclear power plant as described in any one of claims 1 to 4 are implemented.
