Method and system for determining the impact of nuclear power plant changes on fire probabilistic safety analysis

Abstract

The present invention relates to a method for judging the influence of nuclear power plant changes on fire probability safety analysis, the method comprising the following steps: step (1), obtaining change information; step (2), obtaining a preset judgment strategy, wherein the preset judgment strategy includes at least one judgment rule; and any one of the judgment rules corresponds to two judgment results; step (3), judging the change information according to at least one judgment rule, and determining a judgment conclusion of the influence of the change information on the fire probability safety analysis according to the corresponding judgment result. The present invention solves the current situation that there is no method for judging and screening whether the design change of a nuclear power plant affects the fire probability safety analysis in China, solves the problem of design change judgment that needs to be solved urgently during the operation of a nuclear power plant, and improves the effectiveness of managing design changes through a detailed process.

Description

Technical Field

[0001] The present invention belongs to the technical field of fire probability safety analysis, and in particular relates to a method and system for judging the impact of nuclear power plant changes on fire probability safety analysis. Background Art

[0002] Internal fire is an important disaster event that affects the safety of nuclear power plants. The probabilistic safety analysis (PSA) method is widely used internationally to assess the risks it poses to nuclear power plants. Fire PSA is a probabilistic safety analysis of the internal fire risk of nuclear power plants. It quantifies the overall risk of internal fire in nuclear power plants by evaluating the ignition frequency, fire consequences and power plant response of all fire compartments within the power plant boundary, identifies possible weaknesses in the fire protection design of nuclear power plants, and thus provides comprehensive insights into internal fire risks for nuclear power plants.

[0003] There are a large number of design changes in nuclear power plants during construction and operation. Design changes will affect many aspects such as nuclear power plant operation safety and economic costs. There may also be potential fire risks. However, there is currently a lack of methods in China to judge the impact of nuclear power plant design changes on fire PSA, and nuclear power plants cannot reasonably judge the impact of design changes on fire PSA risks. Summary of the invention

[0004] In view of the defects existing in the prior art, the purpose of the present invention is to provide a method and system for determining the impact of nuclear power plant changes on fire probability safety analysis.

[0005] To achieve the above purpose, the technical solution adopted by the present invention is: a method for determining the impact of nuclear power plant changes on fire probability safety analysis, comprising the following steps:

[0006] Step (1), obtaining change information;

[0007] Step (2), obtaining a preset judgment strategy, wherein the preset judgment strategy includes at least one judgment rule; and any judgment rule corresponds to two judgment results;

[0008] Step (3): judging the change information according to at least one judgment rule, and determining a judgment conclusion on the impact of the change information on the fire probability safety analysis according to the corresponding judgment result.

[0009] Furthermore, the preset judgment strategy includes a preliminary judgment strategy and a detailed judgment strategy. The preliminary judgment strategy includes the following judgment rules:

[0010] Determine whether the change information is within the power plant boundary defined by the fire PSA, if yes, enter the detailed judgment strategy;

[0011] Determine whether the changed information will result in changes to the accident procedures or fire management procedures;

[0012] The detailed judgment strategy includes the following judgment rules:

[0013] Determine whether the change information affects the fire PSA elements.

[0014] Further, it is determined whether the change information is within the power plant boundary defined by the fire PSA. If yes, a detailed determination strategy is entered, including:

[0015] Determine whether the change information is within the power plant boundary defined by the fire PSA, and whether the change information affects the normal and emergency operation of the reactor, support systems, and power production;

[0016] If the change information is within the power plant boundary defined by the fire PSA, the detailed judgment strategy is entered;

[0017] If the change information is outside the power plant boundary defined by the fire PSA, and the change information affects the normal and emergency operation of the reactor, the support system and power production, the power plant boundary defined by the fire PSA will be expanded so that the change information is within the power plant boundary defined by the fire PSA, and the detailed judgment strategy will be entered.

[0018] Furthermore, the fire PSA elements include the internal event PSA model, fire compartment boundaries, fire PSA equipment list, fire PSA cable list and temporary fire influencing factors.

[0019] Furthermore, judging whether the change information affects the fire PSA elements specifically includes:

[0020] Determine whether the change information affects the internal event PSA model;

[0021] Determine whether the change information results in a change in the fire compartment boundary;

[0022] Determine whether the change information results in a change in the fire PSA equipment list;

[0023] Determine whether the changed information results in a change in the fire PSA cable list;

[0024] Determine whether the change information results in a change in the temporary fire impact factor.

[0025] Furthermore, judging whether the change information results in a change in the fire PSA equipment list also includes:

[0026] Determine whether the changed equipment is a fixed ignition source;

[0027] Determine whether the changed equipment will affect the incident mitigation measures.

[0028] Further, fixed ignition sources include: batteries, reactor coolant pumps, main control panels, diesel generators, air compressors, battery chargers, clothes dryers, electric motors, electrical cabinets, high-energy arcs, hydrogen tanks, other hydrogen fires, pumps and large hydraulic valves, reactor protection system motor generator sets, transformers, ventilation subsystems, other substation equipment, boilers, main feedwater pumps, turbine and generator exciters, turbine and generator set hydrogen, and turbine and generator set oil.

[0029] The technical solution adopted by the present invention also discloses a judgment system for the impact of nuclear power plant changes on fire probability safety analysis, including:

[0030] An information acquisition unit, used for acquiring change information;

[0031] A strategy acquisition unit, used to acquire a preset judgment strategy;

[0032] An analysis and judgment unit, used to judge the change information according to at least two judgment rules;

[0033] The result output unit is used to determine the judgment conclusion of the impact of the change information on the fire probability safety analysis according to the corresponding judgment result.

[0034] The technical solution adopted by the present invention also discloses a device for judging the impact of nuclear power plant changes on fire probability safety analysis, including a memory and a processor, the memory stores a computer program, and the processor implements the above-mentioned method for judging the impact of nuclear power plant changes on fire probability safety analysis when executing the computer program.

[0035] The technical solution adopted by the present invention also discloses a computer-readable storage medium on which a computer program is stored. When the computer program is executed by a processor, the above-mentioned method for determining the impact of nuclear power plant changes on fire probability safety analysis is implemented.

[0036] The effect of the present invention is that the present invention solves the current situation in China where there is no method for judging and screening whether design changes of nuclear power plants affect fire probability safety analysis, solves the design change judgment problem that needs to be solved urgently during the operation of nuclear power plants, and improves the effectiveness of managing design changes through detailed processes. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] Figure 1 is a flow chart of the preliminary judgment strategy of the method of the present invention;

[0038] Figure 2 It is a flow chart of the detailed judgment strategy of the method of the present invention. DETAILED DESCRIPTION

[0039] The present invention is further described below in conjunction with the accompanying drawings and specific embodiments.

[0040] Embodiment 1

[0041] like Figure 1 As shown, this embodiment provides a method for determining the impact of changes in a nuclear power plant on fire probability safety analysis, comprising the following steps:

[0042] Step (1), obtain change information; internal fire PSA requires a lot of power plant design information support. Identifying the impact of power plant design information changes on fire PSA is conducive to enabling the fire PSA model to continue to provide effective risk insights. Change information includes location information, type information and equipment information of the change.

[0043] Step (2), obtaining a preset judgment strategy; the preset judgment strategy includes at least one judgment rule; and any judgment rule corresponds to two judgment results. In other words, the judgment strategy needs to be preset, and each judgment rule corresponds to two judgment results, namely yes or no, thereby reflecting whether the change information has an impact on the fire PSA or not.

[0044] It is worth noting that the preset judgment strategy of this embodiment includes a preliminary judgment strategy and a detailed judgment strategy, such as Figure 1 As shown, the preliminary judgment strategy of this embodiment includes the following judgment rules:

[0045] First, determine whether the change information is within the power plant boundary defined by the fire PSA. If so, enter the detailed judgment strategy; because if the change information is outside the power plant boundary defined by the fire PSA and does not affect the normal and emergency operation of the reactor, the support system and power production (such as the turbine plant), it means that the change information has no effect on the fire PSA. If important power plant equipment is added outside the power plant boundary defined by the fire PSA, it will affect the normal and emergency operation of the reactor, the support system and power production (such as the turbine plant). Then, expand the fire PSA power plant boundary so that the fire PSA power plant boundary can cover the location of the change information, so that the change information is within the power plant boundary defined by the fire PSA, thereby ensuring that all information that affects the fire PSA after the preliminary judgment strategy enters the detailed judgment strategy for re-judgment.

[0046] Secondly, determine whether the change information leads to changes in accident procedures or fire management procedures. If so, it means that the change information will affect the fire PSA model event sequence analysis and personnel reliability analysis.

[0047] Next, the detailed judgment strategy is further introduced. The detailed judgment strategy includes the following judgment rules:

[0048] That is, determine whether the change information affects the fire PSA elements. If the change information affects the fire PSA elements, it means that the change information has an impact on the fire PSA. In this embodiment, the fire PSA elements include the internal event PSA model, the fire compartment boundary, the fire PSA equipment list, the fire PSA cable list and the temporary fire impact factor. Then, determining whether the change information affects the fire PSA elements is specifically divided into the following five steps:

[0049] Determine whether the change information affects the internal event PSA model; if the change item affects the internal event PSA model structure, it will correspondingly affect the fire PSA model, otherwise, continue with the following steps.

[0050] Determine whether the change information leads to changes in the fire compartment boundary. The fire barrier status of the fire compartment boundary, such as walls, floors, fire doors, fire blocking, etc., will affect the fire compartment division. If the change item affects the change of the fire compartment boundary, it will affect the fire PSA model accordingly. Otherwise, continue with the following steps.

[0051] Determine whether the change information leads to a change in the fire PSA equipment list; the fire PSA equipment refers to the power plant equipment involved in the fire PSA power plant response model. The increase, reduction, functional change or layout room change of the fire PSA equipment will affect the fire PSA equipment list, and further judgment is required on the changed equipment. It is necessary to determine whether the changed equipment belongs to a fixed ignition source, which is a device permanently installed in the fire compartment that may cause a fire. Fixed ignition sources include: batteries, reactor coolant pumps, main control panels, diesel generators, air compressors, battery chargers, dryers, motors, electrical cabinets, high-energy arcs, hydrogen tanks, other hydrogen fires, pumps and large hydraulic valves, reactor protection system electric generator sets, transformers, ventilation subsystems, other substation equipment, boilers, main feedwater pumps, turbine and generator exciters, turbine and generator hydrogen and turbine and generator oil. The increase or decrease of ignition sources in the room will affect the ignition frequency calculation and fire simulation analysis. Next, it is necessary to determine whether the changed equipment will affect the accident mitigation measures. If the changed equipment affects the automatic response or manual response process of the power plant after the accident, changes the normal operation list of the system or changes the normal state of certain valves, it will affect the fire PSA model. In other words, if the change item causes a change in the fire PSA equipment list and the changed equipment is a fixed ignition source or the changed equipment affects the accident mitigation measures, it will affect the fire PSA model accordingly. Otherwise, continue with the following steps.

[0052] Determine whether the change information results in a change in the fire PSA cable list; the fire PSA cable is the cable associated with the fire PSA equipment. If the cables associated with the fire PSA equipment are increased, decreased, laid in rooms, powered, or fire-protected, the fire PSA cable list, ignition source frequency calculation, and circuit failure analysis will be affected. If the change item affects the change in the fire PSA cable list, it will affect the fire PSA model accordingly. Otherwise, continue with the following steps.

[0053] Determine whether the change information leads to a change in the temporary fire impact factor. Temporary fire impact factors include maintenance work, personnel residence, combustible storage, etc. The impact of the change in the temporary fire impact factor on the risk is shown in Table 1 below:

[0054] Table 1 Temporary fire impact factor description

[0055]

[0056]

[0057] Therefore, it is necessary to determine whether the change information leads to a change in the temporary fire impact factor. Regardless of whether the risk of the temporary fire impact factor changes from high to low or from low to high, it will affect the calculation of the ignition source frequency and thus affect the fire PSA model.

[0058] Step (3), judging the change information according to at least one judgment rule, and determining the judgment conclusion of the change information's influence on the fire probability safety analysis according to the corresponding judgment result. It should be noted that the present embodiment presets a plurality of judgment rules, so in actual use, one or more judgment rules can be set according to actual needs. Generally speaking, when judging a plurality of judgment rules one by one, as long as one of the judgment results is yes, then the judgment conclusion that the change information has an influence on the fire probability safety analysis can be obtained. In the present embodiment, the detailed judgment strategy is performed after satisfying the judgment that the change information is within the power plant boundary defined by the fire PSA, that is, judging whether the change information affects the fire PSA element and judging whether the change information causes the accident procedure or the fire management procedure to change only requires one rule to have a judgment result of yes, then the change information has an influence on the fire PSA, and judging whether the change information affects the fire PSA element and judging whether the change information causes the accident procedure or the fire management procedure to change only requires one rule to have a judgment result of no, then the change information has no influence on the fire PSA.

[0059] The present embodiment also discloses a judgment system for the impact of nuclear power plant changes on fire probability safety analysis, the system includes an information acquisition unit, a strategy acquisition unit, an analysis and judgment unit and a result output unit, the information acquisition unit is used to acquire change information; the strategy acquisition unit is used to acquire a preset judgment strategy; the analysis and judgment unit is used to judge the change information according to at least two judgment rules; the result output unit is used to determine the judgment conclusion of the impact of the change information on the fire probability safety analysis according to the corresponding judgment result.

[0060] The division of the functional units in the above examples is not unique, and can be adaptively adjusted according to actual conditions. For example, each functional unit can be divided according to each function, or two or more functions can be integrated into one processing unit; the above integrated unit can be implemented in the form of hardware or in the form of software functional units. It should be noted that the division of units in the embodiments of the present invention is schematic, which is only a logical function division, and there may be other division methods in actual implementation.

[0061] Specifically, the system and method are carried on a computer device for judging the impact of changes in a nuclear power plant on fire probability safety analysis, and the computer device includes a processor and a memory; the memory is used to store computer execution instructions, and the processor and the memory are connected through a bus. The processor executes the computer execution instructions stored in the memory, and the communication device is responsible for connecting to the external network to perform the data receiving and sending process; the processor is connected to the memory, and the memory includes database software; the processor and the memory contain several instructions to enable a personal computer or server or network device to execute all or part of the steps of this method; the types of processors used include central processing units, general-purpose processors, digital signal processors, application-specific integrated circuits, field programmable gate arrays or other programmable logic devices, transistor logic devices, hardware components or any combination thereof; the storage medium includes a USB flash drive, a mobile hard disk, a read-only memory, a random access memory, a disk or an optical disk.

[0062] Specifically, the software system is partially carried by a central processing unit (CPU), a general processor, a digital signal processor (DSP), an application-specific integrated circuit (ASIC), a field programmable gate array (FPGA) or other programmable logic devices, transistor logic devices, hardware components or any combination thereof. It can implement or execute various exemplary logic boxes, modules and circuits described in conjunction with the contents of the present invention. The processor can also be a combination that implements computing functions, such as a combination of one or more microprocessors, a combination of DSP and microprocessor, and the like. The communication equipment for communication between relevant personnel and users can use a transceiver, a transceiver circuit or a communication interface, etc.

[0063] Embodiment 2

[0064] As another embodiment of the present invention, the influence of the change of the control wiring of the incoming switch cabinet is judged by taking the change of the nuclear power plant as an example to judge the influence of the fire probability safety analysis. In step (1), the change information is obtained, including the location information of the control wiring, the type information of the electrical and the equipment information of the incoming switch cabinet. In step (1), the judgment results of each judgment rule are shown in Table 2 below:

[0065] Table 2 Incoming switch cabinet control wiring change judgment process table

[0066]

[0067] The result of the judgment in step (3) of this embodiment is that the design change has an impact on the internal fire PSA, and may affect technical elements such as the fire PSA cable list, ignition frequency calculation and circuit failure analysis, and has an impact on the fire risk.

[0068] Embodiment 3

[0069] As another embodiment of the present invention, the influence of the change of the nuclear power plant on the fire probability safety analysis is judged by taking the change of adding a safety valve to the main water supply pipeline as an example. In step (1), the change information is obtained, including the location information of the safety valve, the type information of the machinery and equipment information of the main water supply pipeline. In step (1), the judgment results of each judgment rule are shown in Table 3 below:

[0070] Table 3 Main water supply pipeline adding safety valve change judgment process table

[0071]

[0072]

[0073] The result of the judgment in step (3) of this embodiment is that the design change has no effect on the internal fire PSA.

[0074] Those skilled in the art will appreciate that in one or more of the above examples, the functions described in the present invention may be implemented in hardware, software, firmware, or any combination thereof. When implemented using software, the functions may be stored in a computer-readable medium or transmitted as one or more instructions or codes on a computer-readable medium. Computer-readable media include computer storage media and communication media, wherein communication media include any media that facilitates the transmission of a computer program from one place to another. The storage medium may be any available medium that a general or special-purpose computer can access.

[0075] Those skilled in the art should understand that the method and system of the present invention are not limited to the embodiments in the specific implementation mode, and the above specific description is only for the purpose of explaining the present invention, and is not used to limit the present invention. Those skilled in the art can derive other implementation modes based on the technical solution of the present invention, which also belong to the technical innovation scope of the present invention, and the protection scope of the present invention is defined by the claims and their equivalents.

Claims

1. A method for determining the impact of nuclear power plant changes on fire probability safety analysis, characterized in that: The following steps are involved: Step (1), obtaining change information, the change information including the changed location information, type information and device information; Step (2), obtaining a preset judgment strategy, wherein the preset judgment strategy includes at least one judgment rule; Any of the judgment rules corresponds to two judgment results; the preset judgment strategy includes a preliminary judgment strategy and a detailed judgment strategy, and the preliminary judgment strategy includes the following judgment rules: Determine whether the change information is within the power plant boundary defined by the fire PSA, if yes, enter the detailed judgment strategy, specifically including: determine whether the change information is within the power plant boundary defined by the fire PSA, determine whether the change information affects the normal and emergency operation of the reactor, the support system and the power production; if the change information is within the power plant boundary defined by the fire PSA, enter the detailed judgment strategy; if the change information is outside the power plant boundary defined by the fire PSA, the change information affects the normal and emergency operation of the reactor, the support system and the power production, then expand the power plant boundary defined by the fire PSA, so that the change information is within the power plant boundary defined by the fire PSA, and enter the detailed judgment strategy; Determining whether the change information results in a change in the accident procedures or fire management procedures; The detailed judgment strategy includes the following judgment rules: Determine whether the change information affects the fire PSA elements; the fire PSA elements include the internal event PSA model, the fire compartment boundary, the fire PSA equipment list, the fire PSA cable list and the temporary fire impact factor; Step (3): judging the change information according to at least one of the judgment rules, and determining a judgment conclusion on the impact of the change information on the fire probability safety analysis according to the corresponding judgment result.

2. The method for determining the impact of nuclear power plant changes on fire probability safety analysis according to claim 1, characterized in that: The determining whether the change information affects the fire PSA element specifically includes: Determine whether the change information affects the internal event PSA model; Determining whether the change information results in a change in the fire compartment boundary; Determining whether the change information results in a change in the fire PSA equipment list; Determining whether the change information results in a change in the fire PSA cable list; Determine whether the change information results in a change in the temporary fire impact factor.

3. The method for determining the impact of nuclear power plant changes on fire probability safety analysis according to claim 2, characterized in that: The determining whether the change information results in a change in the fire PSA equipment list also includes: Determine whether the changed equipment is a fixed ignition source; Determine whether the changed equipment will affect the incident mitigation measures.

4. The method for determining the impact of nuclear power plant changes on fire probability safety analysis according to claim 3, characterized in that: The fixed ignition sources include: batteries, reactor coolant pumps, main control panels, diesel generators, air compressors, battery chargers, clothes dryers, electric motors, electrical cabinets, high-energy arcs, hydrogen tanks, other hydrogen fires, pumps and large hydraulic valves, reactor protection system electric generator sets, transformers, ventilation subsystems, other substation equipment, boilers, main feedwater pumps, turbine and generator exciters, turbine and generator hydrogen, and turbine and generator oil.

5. A system for implementing the method for determining the impact of nuclear power plant changes on fire probability safety analysis as described in any one of claims 1 to 4, characterized in that: include: An information acquisition unit, used for acquiring change information; A strategy acquisition unit, used to acquire a preset judgment strategy; An analysis and judgment unit, configured to judge the change information according to at least two of the judgment rules; The result output unit is used to determine the judgment conclusion of the impact of the change information on the fire probability safety analysis according to the corresponding judgment result.

6. A device for determining the impact of nuclear power plant changes on fire probability safety analysis, characterized in that: The invention comprises a memory and a processor, wherein the memory stores a computer program, and the processor implements the method for determining the influence of a change in a nuclear power plant on a fire probability safety analysis as described in any one of claims 1 to 4 when executing the computer program.

7. A computer-readable storage medium having a computer program stored thereon, characterized in that: When the computer program is executed by a processor, the method for determining the impact of nuclear power plant changes on fire probability safety analysis as described in any one of claims 1 to 4 is implemented.

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