CN115597010A - Capacity-modeling system breach position diagnosis method, system, device and storage medium - Google Patents
Capacity-modeling system breach position diagnosis method, system, device and storage medium Download PDFInfo
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- CN115597010A CN115597010A CN202211246431.7A CN202211246431A CN115597010A CN 115597010 A CN115597010 A CN 115597010A CN 202211246431 A CN202211246431 A CN 202211246431A CN 115597010 A CN115597010 A CN 115597010A
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- 238000003745 diagnosis Methods 0.000 title claims abstract description 42
- 238000000034 method Methods 0.000 title claims abstract description 27
- 239000007788 liquid Substances 0.000 claims abstract description 177
- 230000008859 change Effects 0.000 claims abstract description 133
- 239000000126 substance Substances 0.000 claims abstract description 92
- 238000002347 injection Methods 0.000 claims abstract description 51
- 239000007924 injection Substances 0.000 claims abstract description 51
- 239000003381 stabilizer Substances 0.000 claims abstract description 33
- 238000007599 discharging Methods 0.000 claims abstract description 17
- 238000004364 calculation method Methods 0.000 claims abstract description 10
- 238000004590 computer program Methods 0.000 claims description 9
- 238000002405 diagnostic procedure Methods 0.000 claims description 5
- 238000002955 isolation Methods 0.000 abstract description 6
- 239000002826 coolant Substances 0.000 abstract description 5
- 230000006870 function Effects 0.000 description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- 238000006243 chemical reaction Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 239000000243 solution Substances 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 1
- 238000005229 chemical vapour deposition Methods 0.000 description 1
- 238000012938 design process Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000010606 normalization Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F17—STORING OR DISTRIBUTING GASES OR LIQUIDS
- F17D—PIPE-LINE SYSTEMS; PIPE-LINES
- F17D5/00—Protection or supervision of installations
- F17D5/02—Preventing, monitoring, or locating loss
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F17—STORING OR DISTRIBUTING GASES OR LIQUIDS
- F17D—PIPE-LINE SYSTEMS; PIPE-LINES
- F17D1/00—Pipe-line systems
- F17D1/08—Pipe-line systems for liquids or viscous products
- F17D1/14—Conveying liquids or viscous products by pumping
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F17—STORING OR DISTRIBUTING GASES OR LIQUIDS
- F17D—PIPE-LINE SYSTEMS; PIPE-LINES
- F17D3/00—Arrangements for supervising or controlling working operations
- F17D3/01—Arrangements for supervising or controlling working operations for controlling, signalling, or supervising the conveyance of a product
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F17—STORING OR DISTRIBUTING GASES OR LIQUIDS
- F17D—PIPE-LINE SYSTEMS; PIPE-LINES
- F17D3/00—Arrangements for supervising or controlling working operations
- F17D3/18—Arrangements for supervising or controlling working operations for measuring the quantity of conveyed product
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The invention discloses a method, a system, a device and a storage medium for diagnosing a breach position of a chemical capacitance system, wherein the diagnosing method comprises the steps of obtaining a first liquid level change value of a voltage stabilizer connected with the chemical capacitance system in a first preset time period after an upper charging pipeline and a lower discharging pipeline in an isolation chemical capacitance system; acquiring the net injection flow of the shaft seal of the chemical volume system in a first preset time period, and obtaining a liquid level change set value of the pressure stabilizer according to the net injection flow of the shaft seal; comparing the first liquid level change value with a liquid level change set value to obtain a comparison result; outputting the diagnosis information of the crevasse position according to the comparison result; automatic calculation can be realized, and whether the position of the break is positioned on the chemical volume system or not can be judged quickly and effectively after the break accident happens, so that the accident can be handled in time, and the emission of a primary circuit coolant is reduced.
Description
Technical Field
The invention relates to the technical field of nuclear power plant control rooms, in particular to a chemical capacitance system breach position diagnosis method, system, device and storage medium.
Background
Among a plurality of systems of a nuclear power plant, a primary loop system is an important barrier for guaranteeing nuclear safety, and in the aspect of preventing leakage of primary loop radioactive substances, a large amount of analysis is carried out during the design process of the nuclear power plant, and corresponding regulations are formulated.
Aiming at the accident of a loop system with a tiny break, the accident operation rule is used for controlling the accident. However, in the actual procedure execution process, the operator is required to perform manual calculation, and the static graph is combined to determine whether the breach position is located on the capacity control system belonging to a loop auxiliary system. The whole judgment process needs longer time, is not beneficial to accident handling, and simultaneously can cause more discharge of primary circuit coolant. How to quickly and effectively judge whether the position of the break is positioned on the chemical capacitance system becomes a concern of designers of nuclear power plants.
Disclosure of Invention
The invention aims to provide a capacity-change system breach position diagnosis method, a capacity-change system breach position diagnosis system, a capacity-change system breach position diagnosis device and a storage medium.
The technical scheme adopted by the invention for solving the technical problems is as follows: the method for automatically diagnosing the breach position of the chemical capacitance system of the nuclear power plant is constructed, and comprises the following steps:
s1: after an upper charging pipeline and a lower discharging pipeline in the chemical capacitance system are isolated, acquiring a first liquid level change value of a voltage stabilizer connected with the chemical capacitance system within a first preset time period;
s2: acquiring the net injection flow of the shaft seal of the chemical volume system in the first preset time period, and acquiring a liquid level change set value of the pressure stabilizer according to the net injection flow of the shaft seal;
s3: comparing the first liquid level change value with the liquid level change set value to obtain a comparison result;
s4: and outputting the diagnosis information of the crevasse position according to the comparison result.
Preferably, in the step S1, the obtaining the first liquid level variation value includes the following steps:
s11: acquiring a second liquid level change value of the voltage stabilizer 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;
s12: and 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.
Preferably, in the step S12, the first liquid level variation value is calculated according to an equation a:
wherein L is T Representing said first level variation value, L 10 Represents the firstA value of change in two liquid levels, T representing the first predetermined time period, T 10 Representing the second preset time period.
Preferably, in the step S2, the liquid level change set value is calculated according to an equation b, where the equation b is:
wherein Δ L represents the set value of the level variation, Q 10 Represents the net shaft seal injection flow, T represents the first predetermined time period, and S represents the cross-sectional area of the stabilizer.
Preferably, the obtaining of the shaft seal net injection flow of the chemical volume system in the first preset time period comprises the following steps:
s21: acquiring the main pump shaft seal injection flow of the chemical volume system in the first preset time period;
s23: acquiring main pump shaft seal backflow flow of the chemical volume system in the first preset time period;
s22: and obtaining the net injection flow of the shaft seal according to the injection flow of the main pump shaft seal and the backflow flow of the main pump shaft seal.
Preferably, the comparison result comprises:
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 smaller than the liquid level change set value;
in step S4, the following steps are included:
when the first liquid level change value is larger than or equal to the liquid level change set value, outputting the diagnosis information that the crevasse position is positioned in the chemical volume system;
and when the first liquid level change value is smaller than the liquid level change set value, outputting the diagnosis information that the crevasse position is outside the chemical volume system.
The invention also constructs an automatic diagnosis system for the breach position of the chemical capacitance system of the nuclear power plant, which comprises the following components:
the first execution module is used for acquiring a first liquid level change value of a pressure stabilizer connected with the chemical volume system within a first preset time period after an upper charging pipeline and a lower discharging pipeline in the chemical volume system are isolated;
the second execution module is used for acquiring the net injection flow of the shaft seal of the chemical volume system in the first preset time period and obtaining a liquid level change set value of the pressure stabilizer according to the net injection flow of the shaft seal;
the comparison module is used for comparing the first liquid level change value with the liquid level change set value and obtaining a comparison result;
and the output module is used for outputting the diagnosis information of the crevasse position according to the comparison result.
Preferably, the first execution module includes:
the first obtaining unit is used for obtaining a second liquid level change value of the voltage stabilizer 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;
and the first operation unit is used for 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.
Preferably, the first operation unit obtains the first liquid level variation value by calculation according to an equation a:
wherein L is T Representing said first level variation value, L 10 Represents the second liquid level change value, T represents the first preset time period, T 10 Representing the second preset time period.
Preferably, the second execution module calculates the liquid level change set value according to an equation b, where the equation b is:
wherein Δ L represents the set value of the level variation, Q 10 Represents the net shaft seal injection flow, T represents the first predetermined time period, and S represents the cross-sectional area of the stabilizer.
Preferably, the second execution module includes:
the second acquiring unit is used for acquiring the main pump shaft seal injection flow of the chemical volume system in the first preset time period;
the third obtaining unit is used for obtaining the main pump shaft seal backflow flow of the chemical volume system in the first preset time period;
and the second calculation unit is used for obtaining the net injection flow of the shaft seal according to the main pump shaft seal injection flow and the main pump shaft seal backflow flow.
Preferably, the comparison result comprises:
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 smaller than the liquid level change set value;
the output module outputs the diagnosis information that the crevasse position is positioned in the chemical-volumetric system when the first liquid level change value is larger than or equal to the liquid level change set value;
and the output module outputs the diagnosis information that the crevasse position is positioned outside the chemical capacitance system when the first liquid level change value is smaller than the liquid level change set value.
The invention also constructs an automatic diagnosis device for the breach position of the nuclear power station chemical-volumetric system, which comprises a processor and a memory, wherein the memory stores a computer program, and the processor realizes the steps of the automatic diagnosis method for the breach position of the nuclear power station chemical-volumetric system when executing the computer program.
The invention also relates to a computer-readable storage medium, which stores a computer program that, when being executed by a processor, carries out the steps of the method for automatically diagnosing a breach position of a nuclear power plant chemical containment system.
The implementation of the invention has the following beneficial effects: the automatic diagnosis method for the break position of the chemical capacity system of the nuclear power plant can realize automatic calculation, and quickly and effectively judge whether the break position is positioned on the chemical capacity system after a break accident occurs, so that the accident can be timely handled, and the emission of a primary circuit coolant is reduced.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a flow diagram of a nuclear power plant chemical capacity system breach location automatic diagnostic method of the present invention in some embodiments;
FIG. 2 is a connection diagram of a loop system and a chemical conversion system of a nuclear power plant according to the present invention;
fig. 3 is a flow chart of an automatic diagnosis method for a breach position of a nuclear power plant chemical capacity system according to another embodiment of the invention.
Detailed Description
For a more clear understanding of the technical features, objects, and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
It should be noted that the flow charts shown in the drawings are only exemplary and do not necessarily include all the contents and operations/steps, nor must they be executed in the order described. For example, some operations/steps may be decomposed, and some operations/steps may be combined or partially combined, so that the actual execution sequence may be changed according to the actual situation.
The block diagrams shown in the figures are functional entities only and do not necessarily correspond to physically separate entities. I.e. these functional entities may be implemented in the form of software, or in one or more hardware modules or integrated circuits, or in different networks and/or processor means and/or microcontroller means.
Referring to fig. 1, the present invention constructs an automatic diagnosis method for the breach position of a chemical capacitance system, which can be applied to a nuclear power plant. The diagnosis method can realize automatic calculation, and quickly and effectively judge whether the position of the break is positioned on the chemical volume system 2 after the break accident occurs, thereby timely handling the accident and reducing the emission of the primary loop coolant.
As shown in fig. 1 and 3, the automated diagnosis method for the breach position of the chemical capacitance system comprises the following steps:
s1: after an upper charging pipeline 211 and a lower discharging pipeline 221 in the isolation capacity system 2, acquiring a first liquid level change value of a voltage stabilizer 13 connected with the isolation capacity system 2 within a first preset time period;
it will be appreciated that, in general, and with reference to fig. 2, a primary loop system 1 includes a primary pump 11, a core 12, a pressurizer 13, a steam generator 14, and a primary loop 15 that fluidly couples the primary pump 11, the core 12, the pressurizer 13, and the steam generator 14 together. The chemical volume system 2, which is a primary auxiliary system of the primary loop system 1, has a volume control function that maintains the level of the pressurizer 13 by the fill-up and drain-down functions, thereby maintaining a primary loop water volume.
Generally, referring to fig. 2, the chemical conversion system 2 includes an upper charge line, a lower discharge line, and shaft seal lines, which are respectively connected to the main circuits 15 located at both sides of the main pump 11, and which are shaft-sealed with the main pump of the main pump 11. The charging pipeline comprises a charging pipeline 211, a charging pump 212 and a charging valve 213, the discharging pipeline comprises a discharging pipeline 221 and a discharging valve 222, and the shaft seal pipeline comprises a shaft seal injection pipeline 231 and a shaft seal return pipeline 232. The upper charge line 211 and the lower discharge line 221 are connected to the main circuit 15 on both sides of the main pump 11, respectively, and the upper charge valve 213 opens and closes the upper charge line 211 and the lower discharge valve 222 opens and closes the lower discharge line 221. The chemical vapor deposition system 2 can draw a lower bleed stream from the primary loop system 1 through a lower bleed line 221, and can also pump an upper bleed stream back to the primary loop system 1 through an upper bleed line 211 by an upper charge pump 212. The shaft seal injection pipe 231 and the shaft seal return pipe 232 are respectively connected with the main pump shaft seal of the main pump 11 in a flow guiding manner. The specific connection relationship of the capacitance system 2 can refer to fig. 2, which is not described in detail herein.
After a breach accident occurs, the upper filling and lower discharging functions in the chemical-volumetric system 2 need to be isolated, and only the functions of shaft seal injection and shaft seal backflow are reserved, so that the purpose of ensuring that the source of primary loop inflow water is unique is achieved. The isolation of the upper charging and discharging function, that is, the isolation of the upper charging pipe 211 and the lower discharging pipe 221, may be implemented by closing (stopping) the upper charging pipe 211 and the lower discharging pipe 221 by controlling the upper charging valve 213 and the lower discharging valve 222.
After the upper filling and lower discharging functions in the chemical capacitance system 2 are isolated, the automatic diagnosis method of the breach position of the invention is started to be executed, namely step S1 is executed.
In some embodiments, the manner of obtaining the first liquid level variation value may include:
collecting the liquid level of the voltage stabilizer 13 at a first time point, and recording the liquid level as a first liquid level value;
collecting the liquid level of the voltage stabilizer 13 at a second time point, and recording the liquid level as a second liquid level value;
and obtaining a first liquid level change value according to the first liquid level value and the second liquid level value.
The first preset time period is the time length from a first time point (initial time point) to a second time point (end time point), and the first liquid level change value is the difference value between the second liquid level value and the first liquid level value. In some embodiments, a liquid level meter may be provided within the pressurizer 13, and the current liquid level of the pressurizer 13 is collected by the liquid level meter. Alternatively, the first preset time period may be 30-60min.
S2: acquiring the net injection flow of the shaft seal of the chemical volume system 2 in a first preset time period, and acquiring a liquid level change set value of the pressure stabilizer 13 according to the net injection flow of the shaft seal;
it will be understood that the net shaft seal injection flow rate is the difference between the main pump shaft seal injection flow rate introduced into the main pump shaft seal from the shaft seal injection conduit 231 of the chemical volume system 2 and the main pump shaft seal return flow rate returned to the chemical volume system 2 via the shaft seal return conduit 232 of the chemical volume system 2.
In some embodiments, acquiring the shaft seal net injection flow of the chemical conversion system 2 during the first predetermined period comprises:
acquiring main pump shaft seal injection flow introduced from a shaft seal injection pipeline 231 of the chemical volume system 2 to a main pump shaft seal in a first preset time period;
acquiring main pump shaft seal backflow flow which flows back to the chemical volume system 2 through a shaft seal backflow pipeline 232 of the chemical volume system 2 in a first preset time period;
and calculating to obtain the net injection flow of the shaft seal according to the injection flow of the main pump shaft seal and the backflow flow of the main pump shaft seal.
Optionally, obtaining the main pump shaft seal injection flow and the main pump shaft seal backflow flow can be extracted by means of a DCS system.
In addition, the liquid level change set value is a liquid level change value of the pressurizer 13 corresponding to the net injection flow of the shaft seal in the same time period, different net injection flows of the shaft seal correspond to different liquid level change set values, and all the liquid level change set values can form a linear curve.
In some embodiments, the level change setpoint is calculated according to the following relationship (b), which is specifically:
wherein Δ L represents a set value of liquid level change, Q 10 Representing the net shaft seal injection flow, T representing the first predetermined time period, and S representing the cross-sectional area of the pressurizer 13.
S3: comparing the first liquid level change value with a liquid level change set value to obtain a comparison result;
it will be appreciated that comparing the first level change value with the level change set point is a comparison of the magnitude of the value between the first level change value and the level change set point. The comparison result may include one of the first level change value being greater than the level change set point, the first level change value being less than the level change set point, and the first level change value being equal to the level change set point.
S4: and outputting the diagnosis information of the crevasse position according to the comparison result.
It can be understood that when the break is located in the chemical solution system 2, after the upper filling pipe 211 and the lower draining pipe 221 of the chemical solution system are isolated, the water in the primary circuit system 1 will not leak, and the shaft seal filling water can be filled into the primary circuit system 1 all the time, which causes the liquid level of the primary circuit system 1 (the pressurizer 13) to rise and be greater than the liquid level change set value (equal to or greater than when the shaft seal filling water is not filled).
When the break is located outside the chemical-volumetric system 2, after the upper filling pipe 211 and the lower discharging pipe 221 of the chemical-volumetric system are isolated, the water in the primary loop system 1 will continue to leak, so that the liquid level of the primary loop system 1 (the pressure stabilizer 13) will not rise to the liquid level change set value, that is, will be smaller than the liquid level change set value. When the position of the break is determined to be outside the chemical capacitance system 2, the break is generally on the primary circuit system 1.
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 diagnostic information that the crevasse position is located in the chemical volume system 2 is output; and when the comparison result shows that the first liquid level change value is smaller than the liquid level change set value, the diagnosis information that the crevasse position is outside the chemical volume system 2 is output.
In some embodiments, the method for automatically diagnosing the breach position of the nuclear power plant chemical volume system further comprises displaying diagnostic information that the breach position is located in the chemical volume system 2 or outside the chemical volume system 2.
Referring to fig. 3, in other embodiments, the method for automatically diagnosing the breach position of the nuclear power plant chemical volume system is not favorable for the timeliness of accident handling in view of the fact that the waiting time for acquiring the first liquid level change value is still long (i.e. the first preset time period is too long); in order to shorten the time for acquiring the first liquid level change value, the first liquid level change value is calculated by adopting a normalization mode, so that the time required by judging the position of the break opening is further shortened.
In this embodiment, obtaining a first liquid level change value of the pressure stabilizer 13 connected to the chemical capacitance system 2 in a first preset time period includes the following steps:
s11: acquiring a second liquid level change value of the voltage stabilizer 13 in a second preset time period; the time length of the second preset time period is less than the time length of a preset time period;
s12: and 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.
It is to be understood that, in step S11, obtaining the second liquid level change value of the potentiostat 13 over the second preset time period may include the steps of:
collecting the liquid level of the voltage stabilizer 13 at a third time point, and recording the liquid level as a third liquid level value;
collecting the liquid level of the voltage stabilizer 13 at a fourth time point, and recording the liquid level as a fourth liquid level value;
and obtaining a second liquid level change value according to the third liquid level value and the fourth liquid level value.
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 value between the third liquid level value and the fourth liquid level value. In some embodiments, a liquid level meter may be provided within the pressurizer 13, and the current liquid level of the pressurizer 13 is collected by the liquid level meter. Optionally, the second preset time period may be 10-15 min, which is less than the time length of the first preset time period.
In step S12, the first level variation value is calculated according to equation (a):
wherein L is T Representing a first level variation value, L 10 Represents a second liquid level change value, T represents a first preset time period, T 10 Representing a second preset time period.
It is to be understood that steps S11 to S12 are intended to shorten the time required to obtain the first liquid level variation value by obtaining the liquid level variation value of the pressurizer 13 for a relatively short period of time and calculating it in a normalized manner.
In conclusion, the automatic diagnosis method for the break position of the chemical capacity system of the nuclear power plant realizes the judgment of the micro break position of the primary circuit of the nuclear power plant by utilizing mechanisms such as automatic calculation logic, dynamic judgment and the like, ensures the timeliness of accident handling, reduces the workload of operators for executing accident regulations, and reduces the outward emission of the coolant of the primary circuit.
The invention also constructs an automatic diagnosis system for the breach position of the chemical capacitance system, which can comprise the following components in some embodiments:
the first execution module is configured to obtain a first liquid level change value of the pressure stabilizer 13 connected to the chemical volume system 2 within a first preset time period after the upper charging pipeline 211 and the lower discharging pipeline 221 in the isolation volume system 2 are connected;
the second execution module is used for acquiring the net injection flow of the shaft seal of the chemical volume system 2 in a first preset time period and obtaining a liquid level change set value of the pressure stabilizer 13 according to the net injection flow of the shaft seal;
the comparison module is used for comparing the first liquid level change value with a liquid level change set value and obtaining a comparison result;
and the output module is used for outputting the diagnosis information of the crevasse position according to the comparison result.
In some embodiments, the first execution module may include:
the first acquisition unit is used for acquiring the liquid level of the voltage stabilizer 13 at a first time point and recording the liquid level as a first liquid level value;
the second acquisition unit is used for acquiring the liquid level of the voltage stabilizer 13 at a second time point and recording the liquid level as a second liquid level value;
and the first calculating unit is used for obtaining a first liquid level change value according to the first liquid level value and the second liquid level value.
In some embodiments, the second execution module calculates the liquid level change set point according to equation (b):
wherein Δ L represents a set value of liquid level change, Q 10 Representing the net shaft seal injection flow, T representing the first predetermined time period, and S representing the cross-sectional area of the pressurizer 13.
In some embodiments, the second execution module comprises:
the second obtaining unit is used for obtaining the main pump shaft seal injection flow of the chemical volume system 2 in a first preset time period;
the third obtaining unit is used for obtaining the main pump shaft seal backflow flow of the chemical volume system 2 in a first preset time period;
and the second calculation unit is used for obtaining the net injection flow of the shaft seal according to the injection flow of the main pump shaft seal and the backflow flow of the main pump shaft seal.
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 point, the first liquid level change value being less than the liquid level change set point, and the first liquid level change value being equal to the liquid level change set point.
In some embodiments, the output module outputs the breach position diagnosis information according to the comparison result after receiving the comparison result output by the comparison module. The output module outputs the diagnosis information of the position of the break in the chemical volume system 2 when the comparison result is that the first liquid level change value is greater than or equal to the liquid level change set value; in addition, when the comparison result shows that the first liquid level change value is smaller than the liquid level change set value, the output module outputs the diagnosis information that the crevasse position is outside the chemical capacitance system 2. It will be understood that when the location of the breach is determined to be outside the chemical containment system 2, it generally means that the location of the breach is on the primary system 1.
In some embodiments, the automated system for diagnosing the position of the breach of the chemical capacitive system further comprises a display module for displaying the breach position diagnostic information output by the output module.
In other embodiments, another first execution module is used to replace the first execution module, and other modules (the second execution module, the comparison module and the output module) are the same.
In this embodiment, the another first execution module may include:
a first obtaining unit, configured to obtain a second liquid level change value of the voltage regulator 13 within a second preset time period; the time length of the second preset time period is less than the time length of a preset time period;
and the first operation unit is used for 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.
Preferably, the first acquiring unit may include:
the third acquisition unit is used for acquiring the liquid level of the voltage stabilizer 13 at a third time point and recording the liquid level as a third liquid level value;
the fourth acquisition unit is used for acquiring the liquid level of the voltage stabilizer 13 at a fourth time point and recording the liquid level as a fourth liquid level value;
and the third calculating unit is used for obtaining a second liquid level change value according to the third liquid level value and the fourth liquid level value.
Preferably, the first operation unit calculates the first liquid level variation value according to the following formula (a):
wherein L is T Representing a first level variation value, L 10 Represents a second liquid level change value, T represents a first preset time period, T 10 Representing a second preset time period.
In addition, the invention also constructs an automatic diagnosis device for the breach position of the nuclear power plant chemical-volumetric system, which comprises a processor and a memory stored with a computer program, wherein the processor realizes the steps of the automatic diagnosis method for the breach position of the nuclear power plant chemical-volumetric system when executing the computer program.
The invention also provides a computer-readable storage medium, which stores a computer program, which when executed by a processor implements the steps of the automatic diagnosis method for the breach position of a nuclear power chemical containment system.
It is to be understood that the foregoing examples, while indicating the preferred embodiments of the invention, are given by way of illustration and description, and are not to be construed as limiting the scope of the invention; it should be noted that, for those skilled in the art, the above technical features can be freely combined, and several changes and modifications can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention; therefore, all equivalent changes and modifications made within the scope of the claims of the present invention should be covered by the claims of the present invention.
Claims (14)
1. A nuclear power plant chemical capacity system breach position automatic diagnosis method is characterized by comprising the following steps:
s1: after an upper charging pipeline and a lower discharging pipeline in the chemical capacitance system are isolated, a first liquid level change value of a voltage stabilizer connected with the chemical capacitance system in a first preset time period is obtained;
s2: acquiring the net injection flow of the shaft seal of the chemical volume system in the first preset time period, and acquiring a liquid level change set value of the pressure stabilizer according to the net injection flow of the shaft seal;
s3: comparing the first liquid level change value with the liquid level change set value to obtain a comparison result;
s4: and outputting the diagnosis information of the crevasse position according to the comparison result.
2. The automatic nuclear power plant chemical volume system breach position diagnosis method according to claim 1, wherein, in the step S1, obtaining the first liquid level variation value comprises the steps of:
s11: acquiring a second liquid level change value of the voltage stabilizer 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;
s12: and 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.
3. The automatic diagnostic method for breach position of nuclear power plant chemical volume system according to claim 2, wherein in step S12, the first liquid level variation value is calculated according to formula a:
wherein L is T Representing said first level variation value, L 10 Represents the second liquid level change value, T represents the first preset time period, T 10 Representing the second preset time period.
4. The automatic diagnostic method for breach position of nuclear power plant chemical volume system according to claim 1, wherein in step S2, the liquid level variation set value is calculated according to formula b:
wherein Δ L represents the set value of the level variation, Q 10 Represents the net shaft seal injection flow, T represents the first predetermined time period, and S represents the cross-sectional area of the stabilizer.
5. The automatic diagnostic method for the breach position of nuclear power plant chemical volume system according to claim 1, wherein the step of obtaining the net injection flow of the shaft seal of the chemical volume system in the first preset period comprises the following steps:
s21: acquiring the main pump shaft seal injection flow of the chemical volume system in the first preset time period;
s23: acquiring main pump shaft seal backflow flow of the chemical volume system in the first preset time period;
s22: and obtaining the net injection flow of the shaft seal according to the injection flow of the main pump shaft seal and the backflow flow of the main pump shaft seal.
6. The method for automatically diagnosing the breach position of nuclear power plant chemical volume system according to claim 1, wherein the comparison result comprises:
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 smaller than the liquid level change set value;
in step S4, the following steps are included:
when the first liquid level change value is larger than or equal to the liquid level change set value, outputting the diagnosis information that the crevasse position is positioned in the chemical volume system;
and when the first liquid level change value is smaller than the liquid level change set value, outputting the diagnosis information that the crevasse position is outside the chemical volume system.
7. An automatic diagnostic system for breach positions of a chemical capacity system of a nuclear power plant, comprising:
the first execution module is used for acquiring a first liquid level change value of a pressure stabilizer connected with the chemical volume system within a first preset time period after an upper charging pipeline and a lower discharging pipeline in the chemical volume system are isolated;
the second execution module is used for acquiring the net injection flow of the shaft seal of the chemical volume system in the first preset time period and obtaining a liquid level change set value of the pressure stabilizer according to the net injection flow of the shaft seal;
the comparison module is used for comparing the first liquid level change value with the liquid level change set value and obtaining a comparison result;
and the output module is used for outputting the diagnosis information of the crevasse position according to the comparison result.
8. The automatic diagnostic system for the breach position of nuclear power plant chemical containment system according to claim 7, wherein the first execution module comprises:
the first obtaining unit is used for obtaining a second liquid level change value of the voltage stabilizer 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;
and the first arithmetic unit is used for 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.
9. The automatic diagnostic system for breach position of nuclear power plant chemical-volumetric system of claim 8, wherein the first operation unit obtains the first liquid level variation value by calculation according to formula a:
wherein L is T Represents said first level variation value, L 10 Represents the second liquid level change value, T represents the first preset time period, T 10 Representing the second preset time period.
10. The automatic diagnostic system for breach position of nuclear power plant chemical containment system of claim 7, wherein the second execution module calculates the set value of liquid level change according to formula b:
wherein Δ L represents the set value of the level variation, Q 10 Represents the net shaft seal injection flow, T represents the first predetermined time period, and S represents the cross-sectional area of the stabilizer.
11. The automatic diagnostic system for the breach position of nuclear power plant chemical containment system according to claim 7, wherein the second execution module comprises:
the second obtaining unit is used for obtaining the main pump shaft seal injection flow of the chemical volume system in the first preset time period;
the third acquisition unit is used for acquiring the main pump shaft seal backflow flow of the chemical volume system in the first preset time period;
and the second calculation unit is used for obtaining the net injection flow of the shaft seal according to the main pump shaft seal injection flow and the main pump shaft seal backflow flow.
12. The automatic diagnostic system for breach position of nuclear power plant chemical capacity system of claim 7, wherein the comparison result comprises:
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 smaller than the liquid level change set value;
the output module outputs the diagnosis information that the crevasse position is positioned in the chemical-volumetric system when the first liquid level change value is larger than or equal to the liquid level change set value;
and the output module outputs the diagnosis information that the crevasse position is positioned outside the chemical capacitance system when the first liquid level change value is smaller than the liquid level change set value.
13. An automatic diagnostic device for a breach position of a nuclear power plant chemical volume system, comprising a processor and a memory storing a computer program, wherein the processor implements the steps of the automatic diagnostic method for a breach position of a nuclear power plant chemical volume system according to any one of claims 1 to 6 when executing the computer program.
14. A computer-readable storage medium, characterized in that the computer-readable storage medium stores a computer program, which when executed by a processor, implements the steps of the automatic diagnosis method for a breach location of a nuclear power plant chemical containment system of any of claims 1 to 6.
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