Nuclear power plant fire condition accident diagnosis method and system and readable storage medium
By analyzing the impact of fire compartments on nuclear power plant fire conditions and updating the accident diagnosis logic module, the problem of operator error caused by false information was solved, and accurate accident diagnosis and handling in fire situations were achieved.
Patent Information
- Application Number
- CN202211142685.4
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- Filing Date
- 2022-09-20
- Publication Date
- 2026-02-17
- Estimated Expiration
- 2042-09-20
AI Technical Summary
In the existing technology, false information diagnosis caused by nuclear power plant fires increases the risk of human error by operators and affects the accuracy of accident handling strategies.
A method for diagnosing nuclear power plant fire accidents is constructed. By receiving fire confirmation information input by the operator, the method analyzes the impact of fire compartments, identifies affected parameters using an accident diagnosis guidance information database, updates the accident diagnosis logic module, eliminates false information, and ensures accurate accident diagnosis and handling.
This reduces the need for operators to manually check failure information, lowers the risk of human error, and ensures the accuracy of accident diagnosis and handling in fire situations.
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Figure CN115497655B_ABST
Abstract
Description
TECHNICAL FIELD
[0001] The present application relates to the field of nuclear power plant fire safety, and in particular to a nuclear power plant fire condition accident diagnosis method, system and readable storage medium. BACKGROUND
[0002] Fire is one of the external disasters that must be considered in a nuclear power plant. The fireproof design of a nuclear power plant not only considers reducing the possibility of fire, but also quickly responds to fire accidents to reduce the impact of fire on the unit. A nuclear power plant generally divides fire zones to separate redundant equipment performing the same safety function, and uses fire-fighting facilities such as fire doors and smoke exhaust valves to limit the consequences of a fire in a certain area and prevent the spread of fire to adjacent fire zones.
[0003] The existing accident diagnosis system uses the detected unit state related parameters to make automatic diagnosis logic to give the post-accident unit operating state and accident handling strategy. Among the unit state diagnosis information involved in the nuclear power plant accident handling, the fire may damage the instrument itself or its acquisition cable and power supply cable, and the damage caused by the fire to the digital instrument control system (DCS) cabinet, which will all result in a large amount of false information in the main control room. Using false information to diagnose the unit state will lead the operator to an inappropriate accident handling sequence, and using an accident handling strategy that does not match the actual state of the unit will make the unit state develop in the direction of deterioration. Therefore, the operator must fully consider the information failure caused by the fire to ensure the correct diagnosis of the unit state by the operator under the fire condition, guide the operator to perform the appropriate accident handling sequence, and make the unit retreat or stabilize in a safe state.
[0004] Currently, the operator needs to manually check the relevant failure information list under the fire condition, which increases the risk of human error considering the workload of the operator under the accident condition. SUMMARY
[0005] The technical problem to be solved by the present application is to provide a nuclear power plant fire condition accident diagnosis method, system and readable storage medium to solve the defect of human error risk in the prior art.
[0006] The technical solution adopted by the present application to solve the technical problem is: a nuclear power plant fire condition accident diagnosis method is constructed, comprising the following steps:
[0007] S10, after a fire occurs in a nuclear power plant, receiving fire confirmation information input by an operator, the fire confirmation information including target columns corresponding to the current fire and target fire zones under each target column;
[0008] S20, analyzing the fire impact consequences of each target fire zone respectively to obtain fire impact consequence information;
[0009] S30, determining parameters required for accident diagnosis orientation affected by the current fire according to the fire influence consequence information and the pre-established accident diagnosis orientation information database, and taking the parameters as current affected parameters;
[0010] S40, introducing the fire confirmation signal of the target column and / or the target fire compartment into the accident diagnosis logic module related to the current affected parameters, updating the accident diagnosis logic module, and diagnosing the current acquired unit state information using the updated accident diagnosis logic module.
[0011] Preferably, the fire influence consequence information includes a plurality of first parameters affected by the current fire, and the plurality of first parameters form a first set;
[0012] The accident diagnosis orientation information database includes a plurality of second parameters required for accident diagnosis orientation, and the plurality of second parameters form a second set;
[0013] Step S30 includes:
[0014] Finding the intersection of the first set and the second set, and taking the parameters in the intersection as the current affected parameters.
[0015] Preferably, when the current affected parameters have available redundant parameters,
[0016] Step S40 includes:
[0017] Using the fire confirmation signal of the target column, setting the role result of the current affected parameters in the accident diagnosis logic module to be invalid to update the accident diagnosis logic module;
[0018] Acquiring the parameter value of the redundant parameters from the current acquired unit state information, and diagnosing only the parameter value of the redundant parameters using the updated accident diagnosis logic module.
[0019] Preferably, the current affected parameters include the monitoring effectiveness of the reactor pressure vessel liquid level of at least one column;
[0020] The current acquired unit state information includes the monitoring value and the monitoring effectiveness value of the reactor pressure vessel liquid level of each column;
[0021] Diagnosing the current acquired unit state information using the updated accident diagnosis logic module includes:
[0022] For each column of the reactor pressure vessel liquid level, according to the comparison result of the monitoring value of the reactor pressure vessel liquid level of the corresponding column and the first preset value, and the monitoring validity value of the reactor pressure vessel liquid level of the corresponding column, the intermediate value of the liquid level monitoring of the corresponding column is determined, wherein if the monitoring value of the reactor pressure vessel liquid level of the corresponding column is less than the first preset value, and the monitoring of the reactor pressure vessel liquid level of the corresponding column is valid, the intermediate value of the liquid level monitoring of the corresponding column is high level;
[0023] For each column of the reactor pressure vessel liquid level, the fire confirmation signal of the corresponding column is taken as the complement, and then the logic AND operation is performed with the intermediate value of the liquid level monitoring of the corresponding column to obtain the liquid level monitoring result value of the corresponding column;
[0024] The logic OR operation is performed on the liquid level monitoring result values of all columns to obtain the water inventory recovery strategy execution signal.
[0025] Preferably, when the current affected parameter has an available alternative parameter,
[0026] Step S40 comprises:
[0027] The role result of the current affected parameter in the accident diagnosis logic module is set to invalid using the fire confirmation signal of the target fire compartment, so as to update the accident diagnosis logic module;
[0028] The parameter value of the alternative parameter is obtained from the currently obtained unit state information, and only the parameter value of the alternative parameter is diagnosed using the updated accident diagnosis logic module.
[0029] Preferably, the current affected parameter comprises the monitoring validity of a first instrument, wherein the first instrument is one of a steam radioactivity monitoring instrument arranged in a steam pipeline of a steam generator and a blowdown water radioactivity monitoring instrument arranged in a blowdown water pipeline of the steam generator;
[0030] The currently obtained unit state information comprises the monitoring value and the monitoring validity value of the steam radioactivity monitoring instrument, and the monitoring value and the monitoring validity value of the blowdown water radioactivity monitoring instrument;
[0031] Diagnosing the currently obtained unit state information using the updated accident diagnosis logic module comprises:
[0032] According to the monitoring value and the monitoring validity value of the steam radioactive monitoring instrument, a radioactive monitoring intermediate value of the steam radioactive monitoring instrument is determined; according to the monitoring value and the monitoring validity value of the radioactive monitoring instrument for the blowdown water, a radioactive monitoring intermediate value of the radioactive monitoring instrument for the blowdown water is determined; wherein, if the monitoring value of the steam radioactive monitoring instrument is higher than a second preset value and the monitoring of the steam radioactive monitoring instrument is valid, the radioactive monitoring intermediate value of the steam radioactive monitoring instrument is a high level; if the monitoring value of the radioactive monitoring instrument for the blowdown water is higher than a second preset value and the monitoring of the radioactive monitoring instrument for the blowdown water is valid, the radioactive monitoring intermediate value of the radioactive monitoring instrument for the blowdown water is a high level;
[0033] The fire confirmation signal of the fire compartment where the steam radioactive monitoring instrument is located is inverted, and then a logical AND operation is performed with the radioactive monitoring intermediate value of the steam radioactive monitoring instrument to obtain a monitoring result value of the steam radioactive monitoring instrument; the fire confirmation signal of the fire compartment where the radioactive monitoring instrument for the blowdown water is located is inverted, and then a logical AND operation is performed with the radioactive monitoring intermediate value of the radioactive monitoring instrument for the blowdown water to obtain a monitoring result value of the radioactive monitoring instrument for the blowdown water;
[0034] A logical OR operation is performed on the monitoring result value of the steam radioactive monitoring instrument and the monitoring result value of the radioactive monitoring instrument for the blowdown water to obtain a steam generator heat transfer tube rupture accident strategy execution signal.
[0035] Preferably, the step S40 comprises:
[0036] Using the fire confirmation signal, a diagnosis result of an accident diagnosis logic module related to the current affected parameter is set to a specified result.
[0037] Preferably, the current acquired unit state information is diagnosed using the updated accident diagnosis logic module, comprising:
[0038] It is judged whether the occurrence time of the fire confirmation signal is before the execution time of the accident diagnosis logic module;
[0039] If yes, the accident diagnosis logic module is activated when the fire confirmation signal occurs, and the current acquired unit state information is diagnosed using the updated accident diagnosis logic module;
[0040] If no, the current acquired unit state information is re-diagnosed using the updated accident diagnosis logic module when the fire confirmation signal occurs.
[0041] The application also constructs a readable storage medium, which stores a computer program, and the computer program realizes the steps of the nuclear power plant fire condition accident diagnosis method according to any one of the above when executed by a processor.
[0042] The application also constructs a nuclear power plant fire condition accident diagnosis system, which comprises a processor, and the processor realizes the steps of the nuclear power plant fire condition accident diagnosis method according to the above when executing a stored computer program.
[0043] In the technical solution provided by the application, after receiving the fire confirmation information, the fire influence consequences of each fire compartment can be analyzed, and the parameters required for accident diagnosis (current affected parameters) affected by the fire can be identified and sorted in combination with the accident diagnosis guide information database. Moreover, in the accident diagnosis logic module related to the current affected parameters, the corresponding fire confirmation signal is introduced and participates in the logical processing of the accident diagnosis, thereby providing support for the automatic diagnosis of the accident and ensuring the correct execution of the accident diagnosis and guide under the fire condition. Therefore, compared with the manual review of the related failure list by the operator in the prior art, the risk of human error is avoided. BRIEF DESCRIPTION OF DRAWINGS
[0044] In order to more clearly illustrate the embodiments of the application, the drawings needed in the following embodiment description will be briefly introduced. Obviously, the drawings in the following description are only some embodiments of the application, and other drawings can be obtained by those skilled in the art without creative labor. In the drawings:
[0045] Figure 1 is a flowchart of the nuclear power plant fire condition accident diagnosis method in an embodiment provided by the application;
[0046] Figure 2 is a schematic diagram of the operation interface of the digital monitoring panel;
[0047] Figure 3 is a logic structure diagram of the updated accident diagnosis logic module in an embodiment provided by the application;
[0048] Figure 4 is a logic structure diagram of the updated accident diagnosis logic module in an embodiment provided by the application;
[0049] Figure 5 is a logic structure diagram of the updated accident diagnosis logic module in an embodiment provided by the application. DETAILED DESCRIPTION
[0050] With reference to the accompanying drawings, the technical solutions in the embodiments of the present application will be clearly and completely described in order to make the technical solutions in the embodiments of the present application apparent to those skilled in the art. Obviously, the described embodiments are only a part but not all of the embodiments of the present application. Based on the embodiments in the present application, all the other embodiments obtained by those of ordinary skill in the art without creative work shall fall within the protection scope of the present application.
[0051] Figure 1 is a flowchart of a nuclear power plant fire condition accident diagnosis method in an embodiment provided by the present application. The nuclear power plant fire condition accident diagnosis method in the embodiment includes the following steps.
[0052] S10, after a fire occurs in a nuclear power plant, receiving fire confirmation information input by an operator, the fire confirmation information including target columns corresponding to a current fire and target fire compartments under each target column;
[0053] Regarding this step, first of all, it should be explained that the fire in the nuclear power plant can be detected in the following ways: fire detection system, on-site inspection personnel, camera monitoring system, infrared monitoring system, etc. Moreover, the nuclear power plant fire generally implements a multi-level intervention principle. After discovering a fire, the second-level intervention of fire fighting is started immediately. Only when the fire is confirmed to be unable to be extinguished by existing means and needs the support of professional fire fighting teams, the fire confirmation is needed. As an example, on the operation interface of the digital monitoring panel as shown in Figure 2 The operator can confirm the fire in the corresponding fire compartment by activating the corresponding fire confirmation button, for example, when the user activates the KAE 1001CG button, the fire in the electrical plant (fire compartment) in column A can be confirmed, and at the same time, the indicator light of "A column fire confirmation" will be on (red). It should be understood that when an actual fire occurs, multiple fire compartment buttons may need to be activated at the same time.
[0054] S20, analyzing the fire impact consequences of each target fire compartment respectively to obtain fire impact consequence information;
[0055] Regarding this step, it should be explained that for each fire compartment, in addition to analyzing the direct consequences caused by the fire, such as direct damage to cables or equipment themselves, etc., the consequences of the power-off program implemented after the fire in this fire compartment from the perspective of limiting fire consequences should also be included.
[0056] S30, determining the parameters required for accident diagnosis guidance affected by the current fire according to the fire impact consequence information and the pre-established accident diagnosis guidance information database, and taking them as current affected parameters;
[0057] In this step, as to the accident diagnosis oriented information database, all the information required for the accident treatment can be identified and screened according to the accident treatment procedure, including: state diagnosis parameters, parameters required for the execution of the accident treatment sequence, and further, a complete database of the information required for the accident treatment is established. Among them, the state diagnosis parameters refer to the parameter information required by the accident treatment procedure, for example, including the core neutron flux, the core outlet coolant subcooling degree, the pressure vessel water level, the steam generator radioactivity, the steam generator water level and the like; the parameters required for the execution of the accident treatment sequence include functional state parameters (for example, the high-pressure safety injection flow, the containment spray flow and the like), equipment operating state parameters (such as the main pump operating state, the auxiliary feedwater pump operating state and the like) and the like.
[0058] In the determination of the current affected parameter (the parameter required for the accident diagnosis orientation affected by the current fire), for each parameter in the accident diagnosis oriented information database, the following can be analyzed: whether all the instruments, cables, optical cables, DCS cabinets and the like on the path of the parameter to the main control room are affected by the current fire. Specifically, for each fire compartment, on the one hand, the influence of the fire of the fire compartment on the parameters required for the accident treatment is analyzed; on the other hand, the consequences of the fire of the fire compartment are analyzed, and the accident risks that the fire can cause are identified, for example, for the fire compartment where the pressurizer safety valve is located, the fire of the fire compartment will likely cause the accident consequence of the pressurizer safety valve being stuck open. Therefore, for each fire compartment, the list of affected parameters can be identified according to the analysis result of the fire influence consequences, in combination with the accident diagnosis oriented information database.
[0059] S40, introducing the fire confirmation signal of the target column and / or the target fire compartment into the accident diagnosis logic module related to the current affected parameter, updating the accident diagnosis logic module, and using the updated accident diagnosis logic module to diagnose the current acquired unit state information.
[0060] In this step, in the accident diagnosis logic module related to the current affected parameter, the corresponding fire confirmation signal is introduced and participates in the logical processing of the current affected parameter, so as to eliminate the influence of false information, provide support for the automatic diagnosis of the accident, and ensure the correct execution of the accident diagnosis and orientation under the fire situation.
[0061] Further, in an optional embodiment, the fire influence consequence information includes a plurality of first parameters affected by the current fire, and the plurality of first parameters form a first set. The accident diagnosis oriented information database includes a plurality of second parameters required for the accident diagnosis orientation, and the plurality of second parameters form a second set. Moreover, step S30 includes: finding the intersection of the first set and the second set, and taking the parameters in the intersection as the current affected parameter.
[0062] Further, in an alternative embodiment, if there is a redundant parameter available for the current affected parameter, step S40 comprises: using the fire confirmation signal of the target column, invalidating the result of the current affected parameter in the accident diagnosis logic module to update the accident diagnosis logic module; obtaining the parameter value of the redundant parameter from the current acquired unit state information, and using the updated accident diagnosis logic module to diagnose only the parameter value of the redundant parameter. In this embodiment, for a certain affected parameter, if the current fire only affects the parameter of one column, the parameter does not lose redundancy, and the parameter information of the redundant column is still available. Only the parameter information of the redundant column is listed, and the logic judgment of the accident diagnosis logic module is continued to be executed.
[0063] In a specific embodiment, the current affected parameter comprises the monitoring validity of the reactor vessel level of at least one column, and the redundant parameter comprises the monitoring validity of the reactor vessel level of the other column. The current acquired unit state information comprises the monitoring value and the monitoring validity value (1 represents monitoring validity, and 0 represents monitoring invalidity) of the reactor vessel level of each column. Moreover, in step S40, using the updated accident diagnosis logic module to diagnose the current acquired unit state information comprises:
[0064] For the reactor vessel level of each column, determining the level monitoring intermediate value of the corresponding column according to the comparison result of the monitoring value of the reactor vessel level of the corresponding column and the first preset value, and the monitoring validity value of the reactor vessel level of the corresponding column, wherein if the monitoring value of the reactor vessel level of the corresponding column is less than the first preset value, and the monitoring validity of the reactor vessel level of the corresponding column, the level monitoring intermediate value of the corresponding column is high;
[0065] For the reactor vessel level of each column, performing logical AND operation on the fire confirmation signal of the corresponding column after taking inversion, and the level monitoring intermediate value of the corresponding column to obtain the level monitoring result value of the corresponding column;
[0066] Performing logical OR operation on the level monitoring result values of all columns to obtain the water inventory recovery strategy execution signal.
[0067] In Figure 3In the updated accident diagnosis logic module as shown, if the current affected parameter is the monitoring validity of the reactor vessel level in column A, and at this time, if the monitoring value of the reactor vessel level in column A (LRPV) is lower than the bottom of the reactor primary loop hot leg (B1HL), and the monitoring validity of the reactor vessel level in column A is valid (the monitoring validity value is 1), the AND gate 301 outputs a high level, i.e., the monitoring value of the reactor vessel level in column A is high. Conversely, the monitoring value of the reactor vessel level in column A is low. If the fire confirmation signal in column A is high, i.e., the fire in column A is confirmed, the AND gate 302 outputs a low level, i.e., the monitoring value of the reactor vessel level in column A is low. Thus, the effect of the monitoring value of the reactor vessel level in column A is eliminated when the accident diagnosis logic module executes the diagnosis logic, and only the monitoring values of the reactor vessel level in the other alternative columns (columns B, C, and D) are used to continue executing the diagnosis logic. It should be understood that if the current affected parameter is the monitoring validity of the reactor vessel level in column B or column C or column D, the effect of the monitoring value of the reactor vessel level in the column B or column C or column D is eliminated when the accident diagnosis logic module executes the diagnosis logic, and only the monitoring values of the reactor vessel level in the other alternative columns are used to continue executing the diagnosis logic. Finally, the monitoring values of the reactor vessel level in all columns are sent to the OR gate 303, and the OR gate 303 outputs the water inventory recovery strategy execution signal, i.e., when the OR gate 303 outputs a high level, the water inventory recovery strategy is executed; conversely, the water inventory recovery strategy is not executed.
[0068] Further, in an optional embodiment, if there is an alternative parameter available for the current affected parameter, step S40 comprises: using the fire confirmation signal of the target fire zone to invalidate the effect of the current affected parameter in the accident diagnosis logic module to update the accident diagnosis logic module; obtaining the parameter value of the alternative parameter from the current acquired unit state information, and using the updated accident diagnosis logic module to diagnose only the parameter value of the alternative parameter. In this embodiment, if the fire affects only one parameter signal, but other signals can be used as alternatives, the alternative signals can be listed for the operator to conveniently read and understand the unit state and continue to execute the logic judgment of the accident diagnosis logic module.
[0069] In one embodiment, the current affected parameter includes the monitoring validity of a first instrument, wherein the first instrument is one of a steam radioactivity monitoring instrument arranged in a steam pipe of the steam generator and a blowdown water radioactivity monitoring instrument arranged in a blowdown water pipe of the steam generator. Accordingly, the alternative parameter is the other of the steam radioactivity monitoring instrument and the blowdown water radioactivity monitoring instrument. The current acquired unit state information includes the monitoring value and the monitoring validity value (1 representing valid monitoring and 0 representing invalid monitoring) of the steam radioactivity monitoring instrument, and the monitoring value and the monitoring validity value of the blowdown water radioactivity monitoring instrument. Moreover, the current acquired unit state information is diagnosed using the updated accident diagnosis logic module, including:
[0070] determining a radioactivity monitoring intermediate value of the steam radioactivity monitoring instrument according to the monitoring value and the monitoring validity value of the steam radioactivity monitoring instrument, and determining a radioactivity monitoring intermediate value of the blowdown water radioactivity monitoring instrument according to the monitoring value and the monitoring validity value of the blowdown water radioactivity monitoring instrument; wherein if the monitoring value of the steam radioactivity monitoring instrument is higher than a second preset value and the monitoring of the steam radioactivity monitoring instrument is valid, the radioactivity monitoring intermediate value of the steam radioactivity monitoring instrument is a high level; if the monitoring value of the blowdown water radioactivity monitoring instrument is higher than the second preset value and the monitoring of the blowdown water radioactivity monitoring instrument is valid, the radioactivity monitoring intermediate value of the blowdown water radioactivity monitoring instrument is a high level;
[0071] performing logical AND operation between the fire confirmation signal of the fire compartment in which the steam radioactivity monitoring instrument is arranged and the radioactivity monitoring intermediate value of the steam radioactivity monitoring instrument after the fire confirmation signal is inverted, to obtain a monitoring result value of the steam radioactivity monitoring instrument; performing logical AND operation between the fire confirmation signal of the fire compartment in which the blowdown water radioactivity monitoring instrument is arranged and the radioactivity monitoring intermediate value of the blowdown water radioactivity monitoring instrument after the fire confirmation signal is inverted, to obtain a monitoring result value of the blowdown water radioactivity monitoring instrument;
[0072] performing logical OR operation between the monitoring result value of the steam radioactivity monitoring instrument and the monitoring result value of the blowdown water radioactivity monitoring instrument, to obtain a steam generator heat transfer tube rupture accident strategy (SGTR strategy) execution signal.
[0073] In Figure 4In the shown updated (after the fire confirmation signal of the corresponding fire compartment is introduced) accident diagnosis logic module, if the current affected parameter is the monitoring effectiveness of the steam radioactive monitoring instrument, the alternative parameter is the monitoring effectiveness of the blowdown water radioactive monitoring instrument. At this time, if the monitoring value of the steam radioactive monitoring instrument (SG KRT / VVP) is high in radioactivity, and the monitoring effectiveness of the steam radioactive monitoring instrument (KRT / VVP) is effective, the AND gate 401 outputs a high level, i.e., the radioactivity monitoring intermediate value of the steam radioactive monitoring instrument is high, otherwise, it is low. If the fire confirmation signal of the fire compartment where the steam radioactive monitoring instrument (KRT / VVP) is located is high, i.e., the fire compartment where the steam radioactive monitoring instrument (KRT / VVP) is located confirms a fire, the AND gate 402 outputs a low level, i.e., the radioactivity monitoring result value of the steam radioactive monitoring instrument is low. In this way, when the accident diagnosis logic module executes the diagnosis logic, the effect result of the radioactivity monitoring of the steam radioactive monitoring instrument is eliminated, and only the available radioactivity monitoring value of the blowdown water radioactive monitoring instrument is used to continue to execute the diagnosis logic. It should be understood that if the current affected parameter is the blowdown water radioactive monitoring instrument, when the accident diagnosis logic module executes the diagnosis logic, the effect result of the radioactivity monitoring value of the blowdown water radioactive monitoring instrument is eliminated, and only the radioactivity monitoring value of the steam radioactive monitoring instrument is used to continue to execute the diagnosis logic. Finally, the radioactivity monitoring result values of all the instruments are sent to the OR gate 403. The OR gate 403 outputs the SGTR strategy execution signal, i.e., when the OR gate 403 outputs a high level, the SGTR strategy is executed; otherwise, the SGTR strategy is not executed.
[0074] Further, in an optional embodiment, the step S40 comprises: using the fire confirmation signal to set the diagnosis result of the accident diagnosis logic module related to the current affected parameter to a specified result. In this embodiment, if the fire only affects one of the parameter signals, in order to avoid misleading, the lost signal can be listed for the operator to conveniently read and understand the unit state, and the diagnosis logic of the accident diagnosis logic module is forced to be a specified result.
[0075] In Figure 5In the updated accident diagnosis logic module shown, if the current affected parameter is the validity of the emergency panel voltage acquisition signal of column A, at this time, the LHA panel (emergency panel of column A, used to provide power and control electricity for safety level users) voltage is low (for example, lower than the third preset value), and the LHA panel voltage acquisition signal is valid, the AND gate 501 outputs high level, that is, the monitoring intermediate value of the LHA panel voltage is high level. If the A column fire confirmation signal is high level, that is, column A confirms that a fire occurs, the AND gate 502 outputs low level, that is, the monitoring result value of the emergency panel voltage of column A is low level, and then the AND gate 503 outputs low level, that is, the SBO strategy is not executed, and the diagnosis result of the accident diagnosis logic module is forcibly set to not execute the SBO strategy. It should be understood that if the current affected parameter is the validity of the emergency panel voltage acquisition signal of column B or column C, the AND gate 503 will also output low level, that is, the diagnosis logic of the accident diagnosis logic module is forcibly set to not execute the SBO strategy.
[0076] Further, in an optional embodiment, in step S40, the current acquired unit state information is diagnosed using the updated accident diagnosis logic module, including:
[0077] determining whether the occurrence time of the fire confirmation signal is before the execution time of the accident diagnosis logic module;
[0078] If yes, activating the accident diagnosis logic module at the time of occurrence of the fire confirmation signal, and diagnosing the current acquired unit state information using the updated accident diagnosis logic module;
[0079] If no, re-diagnosing the current acquired unit state information using the updated accident diagnosis logic module at the time of occurrence of the fire confirmation signal.
[0080] In actual application, when the operator inputs the fire confirmation signal on the operation interface of the digital monitoring panel, the automatic accident diagnosis system (including multiple accident diagnosis logic modules) can also be activated by the manual control module, and the computer can finally give an appropriate accident handling strategy according to the current unit state and the influence of the fire on the diagnosis logic. However, considering the different times when the fire is confirmed, there are the following situations:
[0081] (a) The fire is confirmed before the execution of the accident handling procedure;
[0082] (b) The fire is confirmed during the execution of the accident handling procedure:
[0083] For case (a), directly activate the accident automatic diagnosis system, and diagnose the current acquired unit state information using the updated accident diagnosis logic module;
[0084] For case (b), re-execute the accident automatic diagnosis system, and re-diagnose the current acquired unit state information using the updated accident diagnosis logic module.
[0085] The application also provides a computer readable storage medium storing a computer program, and the computer program implements the steps of the nuclear power plant fire condition accident diagnosis method when executed by a processor.
[0086] The computer readable storage medium of the application can be a U disk, a mobile hard disk, a read-only memory (ROM), a magnetic disk or an optical disk, and the like.
[0087] The application also provides a nuclear power plant fire condition accident diagnosis system, which comprises a processor, and the processor implements the steps of the nuclear power plant fire condition accident diagnosis method when executing a stored computer program.
[0088] The processor of the application is used to provide computing and control capabilities to support the operation of the entire nuclear power plant fire condition accident diagnosis system. It should be understood that, in the embodiments of the application, the processor can be a central processing unit (CPU), and the processor can also be other general-purpose processors, digital signal processors (DSP), application specific integrated circuits (ASIC), field-programmable gate arrays (FPGA) or other programmable logic devices, discrete gates or transistor logic devices, discrete hardware components, and the like. The general-purpose processor can be a microprocessor, or the processor can also be any conventional processor.
[0089] The above only describes the preferred embodiments of the application and is not used to limit the application. For those skilled in the art, the application can have various modifications and changes. Any modification, equivalent replacement, improvement and the like made within the spirit and principle of the application shall be included in the scope of the claims of the application.
Claims
1. A method for diagnosing fire-related accidents in nuclear power plants, characterized in that, Includes the following steps: S10, after a fire occurs at the nuclear power plant, receive fire confirmation information input by the operator. The fire confirmation information includes the target column corresponding to the current fire and the target fire protection zone under each target column. S20, analyze the fire impact consequences of each target fire compartment to obtain information on the fire impact consequences; S30, based on the fire impact consequences information and the pre-established accident diagnosis guidance information database, determine the parameters required for accident diagnosis guidance affected by the current fire, and use them as the currently affected parameters; the currently affected parameters include the monitoring effectiveness of at least one column of reactor pressure vessel liquid level. S40, introduce the fire confirmation signal of the target column and / or the target fire compartment into the accident diagnosis logic module related to the current affected parameter, and update the accident diagnosis logic module; The updated accident diagnosis logic module is used to diagnose the currently acquired unit status information; The unit status information currently acquired includes: the monitoring values and monitoring validity values of the reactor pressure vessel liquid levels in each column; When there are available redundant parameters for the currently affected parameters, the diagnosis includes: for each column of reactor pressure vessel liquid level, determining the liquid level monitoring median value of the corresponding column based on the comparison result of the monitored value of the reactor pressure vessel liquid level of the corresponding column with the first preset value, and the monitoring validity value of the reactor pressure vessel liquid level of the corresponding column, wherein if the monitored value of the reactor pressure vessel liquid level of the corresponding column is less than the first preset value, and the monitoring of the reactor pressure vessel liquid level of the corresponding column is valid, then the liquid level monitoring median value of the corresponding column is high level; For each column of reactor pressure vessel liquid level, the fire confirmation signal of the corresponding column is inverted, and then a logical AND operation is performed with the intermediate value of the liquid level monitoring of the corresponding column to obtain the liquid level monitoring result value of the corresponding column. Perform a logical OR operation on the liquid level monitoring results of all columns to obtain the water volume recovery strategy execution signal.
2. The method for diagnosing nuclear power plant fire operating conditions according to claim 1, characterized in that, The fire impact consequences information includes multiple first parameters affected by the current fire, and the multiple first parameters form a first set; The accident diagnosis guidance information database includes multiple second parameters required for accident diagnosis guidance, and the multiple second parameters form a second set; Step S30 includes: Find the intersection of the first set and the second set, and use the parameters in the intersection as the currently affected parameters.
3. A method for diagnosing nuclear power plant fire accidents, characterized in that, Includes the following steps: S10, after a fire occurs at the nuclear power plant, receive fire confirmation information input by the operator. The fire confirmation information includes the target column corresponding to the current fire and the target fire protection zone under each target column. S20, analyze the fire impact consequences of each target fire compartment to obtain information on the fire impact consequences; S30, based on the fire impact consequences information and the pre-established accident diagnosis guidance information database, determine the parameters required for the accident diagnosis guidance affected by the current fire, and use them as the current affected parameters; the current affected parameters include: the monitoring effectiveness of at least one column of first instruments, wherein the first instrument is one of the steam radioactivity monitoring instrument installed in the steam pipe of the steam generator and the sewage radioactivity monitoring instrument installed in the sewage pipe of the steam generator. S40, introduce the fire confirmation signal of the target column and / or the target fire compartment into the accident diagnosis logic module related to the current affected parameter, and update the accident diagnosis logic module; The updated accident diagnosis logic module is used to diagnose the currently acquired unit status information; The unit status information currently acquired includes: the monitoring values and monitoring validity values of the reactor pressure vessel liquid levels in each column; When there are available redundant parameters for the currently affected parameters, the diagnosis includes: for the fire compartment where the steam radioactivity monitoring instrument and / or the wastewater radioactivity monitoring instrument are located, determining the intermediate radioactivity monitoring value of the steam radioactivity monitoring instrument based on the monitoring value and monitoring validity value of the steam radioactivity monitoring instrument; determining the intermediate radioactivity monitoring value of the wastewater radioactivity monitoring instrument based on the monitoring value and monitoring validity value of the wastewater radioactivity monitoring instrument; wherein, if the monitoring value of the steam radioactivity monitoring instrument is higher than a second preset value and the monitoring of the steam radioactivity monitoring instrument is valid, then the intermediate radioactivity monitoring value of the steam radioactivity monitoring instrument is high; if the monitoring value of the wastewater radioactivity monitoring instrument is higher than a second preset value and the monitoring of the wastewater radioactivity monitoring instrument is valid, then the intermediate radioactivity monitoring value of the wastewater radioactivity monitoring instrument is high. For the fire compartment where the steam radioactivity monitoring instrument and / or the wastewater radioactivity monitoring instrument are located, the fire confirmation signal of the fire compartment where the wastewater radioactivity monitoring instrument is located is inverted, and then a logical AND operation is performed with the intermediate value of the radioactivity monitoring of the wastewater radioactivity monitoring instrument to obtain the monitoring result value of the wastewater radioactivity monitoring instrument. The monitoring result value of the steam radioactivity monitoring instrument and the monitoring result value of the wastewater radioactivity monitoring instrument are logically ORed to obtain the steam generator heat transfer tube rupture accident strategy execution signal.
4. The method for diagnosing nuclear power plant fire operating conditions according to claim 3, characterized in that, The fire impact consequences information includes multiple first parameters affected by the current fire, and the multiple first parameters form a first set; The accident diagnosis guidance information database includes multiple second parameters required for accident diagnosis guidance, and the multiple second parameters form a second set; Step S30 includes: Find the intersection of the first set and the second set, and use the parameters in the intersection as the currently affected parameters.
5. A readable storage medium storing a computer program, characterized in that, When the computer program is executed by the processor, it implements the steps of the nuclear power plant fire condition accident diagnosis method according to any one of claims 1-4.
6. A nuclear power plant fire condition accident diagnosis system, comprising a processor, characterized in that, When the processor executes the stored computer program, it implements the steps of the nuclear power plant fire condition accident diagnosis method according to any one of claims 1-4.
Citation Information
Patent Citations
Method and device for handling nuclear power accident
CN107945897A