Internal flooding probability safety analysis method and device for multi-module high-temperature gas cooled reactor nuclear power plant, electronic equipment and storage medium

Abstract

The invention discloses an internal flooding probability safety analysis method and device for a multi-module high-temperature gas cooled reactor nuclear power plant, electronic equipment and a storage medium, the method and device are applied to the electronic equipment, and specifically, flooding partition division, flooding source identification and SSC identification are carried out based on multiple parameters of the multi-module high-temperature gas cooled reactor nuclear power plant. A plurality of water logging feature recognition results are obtained; performing flooding scene analysis and flooding frequency analysis on the multi-module high-temperature gas cooled reactor nuclear power plant based on the multiple flooding feature recognition results to obtain a flooding influence result and a flooding frequency result; and constructing a flooding PSA model based on the flooding influence result and the flooding frequency result, and quantifying the model to obtain an internal flooding risk result of the multi-module high-temperature gas cooled reactor nuclear power plant. According to the scheme, multi-module technical elements are naturally included, and therefore internal water logging probability safety analysis can be carried out on the high-temperature gas cooled reactor nuclear power plant according to the design characteristics of the high-temperature gas cooled reactor multi-module high-temperature gas cooled reactor nuclear power plant.

Description

Technical Field

[0001] The present application relates to the field of nuclear safety analysis of high temperature gas-cooled reactors, and more specifically, to a method, device, electronic equipment and storage medium for internal flooding probabilistic safety analysis of a multi-module high temperature gas-cooled reactor nuclear power plant. Background Art

[0002] As an advanced reactor technology with independent intellectual property rights and characteristics of the fourth generation of nuclear power in my country, the high temperature gas-cooled reactor is highly advanced and safe. In the engineering practice of multi-module high temperature gas-cooled reactor nuclear power plants, in order to ensure that workers, the public and the environment are protected from inappropriate radioactive hazards, nuclear safety analysis, especially probabilistic safety analysis, is a key regulatory requirement of government regulatory authorities. Among them, internal flooding is one of the sources of internal disaster risks in nuclear power plants. In recent years, after a nuclear power plant abroad was flooded by a tsunami and caused a serious nuclear accident, internal flooding has become an internal disaster that the regulatory authorities have paid close attention to. Probabilistic safety analysis of internal flooding (hereinafter referred to as "internal flooding PSA") is an important nuclear safety analysis method that can evaluate the overall flooding risk level of nuclear power plants, thereby identifying design weaknesses, guiding the optimization and improvement of nuclear power plant designs, and ultimately meeting the requirements of nuclear safety regulations and relevant documents of regulatory authorities.

[0003] However, the current traditional internal flooding PSA is aimed at traditional pressurized water reactor nuclear power plants. However, because the multi-module high-temperature gas-cooled reactor nuclear power plant is a typical non-light water reactor, it has the design feature of "multiple modules with one machine", that is, multiple modular reactors are equipped with one steam turbine. Therefore, the traditional internal flooding PSA method cannot adapt to the design features of the multi-module high-temperature gas-cooled reactor nuclear power plant, resulting in its inability to solve the problem of internal flooding probability analysis. Summary of the invention

[0004] In view of this, the present application provides a method, device, electronic equipment and storage medium for internal flooding probabilistic safety analysis of a multi-module high-temperature gas-cooled reactor nuclear power plant, which are used to perform internal flooding probabilistic safety analysis on the multi-module high-temperature gas-cooled reactor nuclear power plant based on its design features.

[0005] In order to achieve the above objectives, the proposed solution is as follows:

[0006] An internal flooding probabilistic safety analysis method for a multi-module high-temperature gas-cooled reactor nuclear power plant is applied to electronic equipment. The internal flooding probabilistic safety analysis method comprises the following steps:

[0007] Based on multiple parameters of a multi-module high-temperature gas-cooled reactor nuclear power plant, flooding zoning, flooding source identification and SSC identification were performed to obtain multiple flooding feature identification results;

[0008] Based on the multiple flooding feature identification results, a flooding scenario analysis is performed on the multi-module high temperature gas-cooled reactor nuclear power plant to obtain the flooding impact result;

[0009] Processing the flooding source identification result to obtain the internal flooding frequency of the multi-module high temperature gas-cooled reactor nuclear power plant;

[0010] Model construction is performed based on the flooding impact result and the internal flooding frequency to obtain a flooding PSA model for safety analysis of the internal flooding frequency.

[0011] Optionally, the flooding zoning, flooding source identification and SSC identification are performed based on multiple parameters of a multi-module high temperature gas-cooled reactor nuclear power plant to obtain multiple flooding feature identification results, including the steps of:

[0012] Dividing flooded zones according to building design information of the multi-module high-temperature gas-cooled reactor nuclear power plant, and identifying common mode failure points of the multi-module reactors based on physical separation between different module reactors of the nuclear power plant;

[0013] Performing SSC identification on the nuclear power plant, finding out the SSC of the flooding initiating event and mitigation facilities affecting the multi-module high temperature gas-cooled reactor nuclear power plant and its impact on the multi-module reactor, and obtaining SSC identification results;

[0014] The flooding sources of the nuclear power plant are identified, potential flooding sources of the nuclear power plant are screened out, and their flooding characteristics and locations are identified to obtain flooding source identification results.

[0015] Optionally, the flooding source identification includes flooding source screening, flooding source feature identification and flooding source location identification.

[0016] Optionally, the flooding PSA model includes a flooding initiating event, an event tree model and a fault tree model.

[0017] Optionally, the performing model building based on the flooding impact result and the internal flooding probability to obtain a flooding PSA model for safety analysis of the internal flooding frequency comprises the steps of:

[0018] Constructing a multi-module flooding initiation event and the multi-module event sequence;

[0019] Establishing a multi-module common system model based on the multi-module event sequence, wherein the multi-module common system model includes system dependencies between multiple module stacks;

[0020] The single-module common cause group and multi-module high-order common cause basic events are set in the multi-module common system model to obtain the flooding PSA model.

[0021] An internal flooding probability safety analysis device for a multi-module high-temperature gas-cooled reactor nuclear power plant is applied to electronic equipment. The internal flooding probability analysis device comprises:

[0022] The qualitative analysis and identification processing module is configured to perform flooding zoning, flooding source identification and SSC identification based on multiple parameters of a multi-module high-temperature gas-cooled reactor nuclear power plant, and obtain multiple flooding feature identification results;

[0023] A PSA modeling scenario analysis module is configured to perform a flooding scenario analysis on the multi-module high temperature gas-cooled reactor nuclear power plant based on the multiple flooding feature identification results to obtain the flooding impact result;

[0024] A quantitative assessment and analysis execution module is configured to process the flooding source identification result to obtain the internal flooding frequency of the multi-module high temperature gas-cooled reactor nuclear power plant;

[0025] The model building module is configured to perform model building based on the flooding impact result and the internal flooding frequency to obtain a flooding PSA model for safety analysis of the internal flooding frequency.

[0026] Optionally, the identification processing module includes:

[0027] A first identification unit is configured to divide flooded zones according to plant design information of the multi-module high temperature gas-cooled reactor nuclear power plant and based on physical divisions between different plant buildings and rooms of the multi-module high temperature gas-cooled reactor nuclear power plant, and identify common mode failure points according to the flooded zones;

[0028] A second identification unit is configured to perform SSC identification on the multi-module high temperature gas-cooled reactor nuclear power plant to obtain an SSC identification result;

[0029] The third identification unit is configured to perform flooding source identification and obtain a flooding source identification result.

[0030] Optionally, the model building module includes:

[0031] An event sequence analysis unit configured to construct a multi-module flooding initiating event and the multi-module event sequence;

[0032] a multi-module correlation analysis unit configured to establish a multi-module common system model based on the multi-module event sequence, wherein the multi-module common system model includes system correlations between a plurality of module stacks;

[0033] The dual common cause failure analysis unit is configured to set a single module common cause group and a multi-module high-order common cause basic event in the multi-module common system model to obtain the flooding PSA model.

[0034] An electronic device, comprising at least one processor and a memory connected to the processor, wherein:

[0035] The memory is used to store computer programs or instructions;

[0036] The processor is used to execute the computer program or instruction so that the electronic device implements the internal flooding probabilistic safety analysis method of the multi-module high-temperature gas-cooled reactor nuclear power plant as described above.

[0037] A computer-readable storage medium is applied to an electronic device, wherein the storage medium carries one or more computer programs, and the one or more computer programs can be executed by the electronic device, so that the electronic device implements the internal flooding probabilistic safety analysis method of a multi-module high-temperature gas-cooled reactor nuclear power plant as described above.

[0038] It can be seen from the above technical scheme that the present application discloses a method, device, electronic device and storage medium for internal flooding probabilistic safety analysis of a multi-module high temperature gas-cooled reactor nuclear power plant. The method and device are applied to electronic devices, specifically to perform flooding zoning, flooding source identification and SSC identification based on multiple parameters of the multi-module high temperature gas-cooled reactor nuclear power plant, and obtain multiple flooding feature identification results; based on multiple flooding feature identification results, perform flooding scenario analysis and flooding frequency analysis on the multi-module high temperature gas-cooled reactor nuclear power plant, and obtain flooding impact results and flooding frequency results; construct a flooding PSA model based on the flooding impact results and flooding frequency results, and obtain the internal flooding risk results of the multi-module high temperature gas-cooled reactor nuclear power plant through quantitative modeling. This scheme naturally includes multi-module technical elements, so it is possible to implement internal flooding probabilistic safety analysis on the design characteristics of the multi-module high temperature gas-cooled reactor nuclear power plant. BRIEF DESCRIPTION OF THE DRAWINGS

[0039] In order to more clearly illustrate the embodiments of the present application or the technical solutions in the prior art, the drawings required for use in the embodiments or the description of the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying creative work.

[0040] Figure 1 This is a flow chart of a method for probabilistic safety analysis of internal flooding in a multi-module high-temperature gas-cooled reactor nuclear power plant according to an embodiment of the present application;

[0041] Figure 2 This is a flow chart of a method for constructing a flooded PSA model according to an embodiment of the present application;

[0042] Figure 3A block diagram of an internal flooding probabilistic safety analysis device for a multi-module high-temperature gas-cooled reactor nuclear power plant according to an embodiment of the present application;

[0043] Figure 4 A block diagram of another internal flooding probabilistic safety analysis device for a multi-module high-temperature gas-cooled reactor nuclear power plant according to an embodiment of the present application;

[0044] Figure 5 A block diagram of an electronic device according to an embodiment of the present application. DETAILED DESCRIPTION

[0045] The following will be combined with the drawings in the embodiments of the present application to clearly and completely describe the technical solutions in the embodiments of the present application. Obviously, the described embodiments are only part of the embodiments of the present application, not all of the embodiments. Based on the embodiments in the present application, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of this application.

[0046] Figure 1 This is a flow chart of a method for probabilistic safety analysis of internal flooding in a multi-module high-temperature gas-cooled reactor nuclear power plant according to an embodiment of the present application.

[0047] like Figure 1 As shown, the internal flooding probability safety analysis method of this embodiment is applied to electronic equipment, and is used to analyze and calculate the internal flooding risk of a multi-module high-temperature gas-cooled reactor nuclear power plant. The electronic equipment here can be understood as a computer, server or cloud platform with data computing and information processing capabilities. The internal flooding probability safety analysis method includes the following steps:

[0048] S1. Perform multiple analysis and processing on the multiple parameters obtained.

[0049] The multiple parameters here refer to the parameters collected from a multi-module high-temperature gas-cooled reactor nuclear power plant equipped with a high-temperature gas-cooled reactor. On this basis, the multiple parameters are divided into flooding zones, flooding sources are identified, and SSC is identified, thereby obtaining multiple flooding feature identification results. The specific identification scheme is as follows:

[0050] Firstly, according to the plant design information of a multi-module high temperature gas-cooled reactor nuclear power plant, water flooding partitions are divided based on the physical division between different modules of the multi-module high temperature gas-cooled reactor nuclear power plant, and the common mode failure points are identified according to the water flooding partitions.

[0051] A flooding partition is a physical object and the smallest unit for flooding analysis. A unit of a high-temperature gas-cooled reactor multi-module high-temperature gas-cooled reactor nuclear power plant is configured with multiple reactor modules. Flooding events in certain flooding partitions will affect multiple reactor modules at the same time. Such flooding partitions are called multi-module reactor common mode failure points, i.e., common mode failure points in this application.

[0052] Then, SSC identification is performed on a multi-module high temperature gas-cooled reactor nuclear power plant to obtain SSC identification results;

[0053] SSC refers to the structures, systems and equipment in a multi-module high-temperature gas-cooled reactor nuclear power plant, Structure, System, Component (SSC) and considers the failure impact of SSC and the liquid system of a multi-module high-temperature gas-cooled reactor nuclear power plant during the identification process, whether it is a single module, dual stack or multiple modules. In the process of SSC identification, first determine whether the equipment will fail due to flooding; then determine whether the failure of the corresponding equipment due to flooding will lead to a flooding initiation event in a multi-module high-temperature gas-cooled reactor nuclear power plant, or whether it will affect the accident mitigation function of a multi-module high-temperature gas-cooled reactor nuclear power plant; further, when determining whether the failure of the corresponding equipment due to flooding will lead to a flooding initiation event or affect the mitigation function, whether it will cause a flooding initiation event in multiple reactor modules, and whether it will cause the accident mitigation function of multiple reactor modules to be affected.

[0054] The SSC identification results mainly include the SSC list. The SSC list contains all the equipment identified by the SSC and the flooding zone where each equipment is located; the flooding failure impact of each equipment in the SSC list, including the flooding initiating event caused by the flooding, the mitigation function, and which reactor modules are affected.

[0055] Finally, based on the flood source identification, the flood source identification result is obtained. Specifically, the flood source identification includes flood source screening, flood source feature identification and flood source location identification.

[0056] Water flooding source screening is to screen out SSCs containing liquid (including but not limited to water) from all SSCs in a multi-module high-temperature gas-cooled reactor nuclear power plant, and then screen the water flooding sources based on factors such as the total liquid amount, design flow rate, and design pressure.

[0057] Flooding source feature identification is to determine the leakage flow, total leakage and flooding type (there are three types of flooding: spraying, flooding and major flooding) when flooding occurs at the flooding source based on system design parameters, determine the upstream and downstream boundaries of the flooding source, determine the impact of the failure of the flooding source system function on the flooding initiation event and mitigation function of the power plant, and further determine which reactor modules are affected by the failure of the flooding source system function.

[0058] The flood source location identification is to determine the flood zone where the flood source is located and the characteristics of the flood source in each flood zone based on the pipeline layout drawing of the flood source system. The characteristics of the same flood source system in different flood zones may be different.

[0059] The final analysis results include the classification of the multi-module impacts of SSC and flooding sources. Taking a 600MW high-temperature gas-cooled reactor multi-module high-temperature gas-cooled reactor nuclear power plant as an example, the unit has a total of 6 reactor modules. The classification results include affecting reactor module No. 1, affecting reactor module No. 2, affecting reactor module No. 3, affecting reactor module No. 4, affecting reactor module No. 5 and affecting reactor module No. 6, and also include affecting reactor modules No. 1 and 2 at the same time, affecting reactor modules No. 3 and 4 at the same time, affecting reactor modules No. 5 and 6 at the same time, affecting reactor modules No. 1, 2 and 3 at the same time, affecting reactor modules No. 4, 5 and 6 at the same time, and affecting all 6 reactor modules at the same time.

[0060] S2. Conduct flooding scenario analysis on a multi-module high-temperature gas-cooled reactor nuclear power plant based on multiple flooding feature identification results.

[0061] Based on the above multiple flood feature identification results, flood scenario analysis is carried out, that is, the single-module, dual-stack and multi-module flood initiating events and the impact on system functions caused by internal flooding are analyzed. The flood scenario refers to the process and result of the flooding event. The analysis method is to calculate the spray range, spread range and flood height of the flood according to the characteristics of the flood source (leakage flow, total leakage), and finally determine which equipment is affected by the flood. Then, based on the impact of equipment flooding failure obtained in the previous analysis steps, determine the final impact of the flood scenario, as well as the flood initiating events caused by the flood and the affected mitigation functions.

[0062] S3. Calculate the flooding frequency and obtain the flooding frequency result.

[0063] By processing the results of multiple flooding source identification, the internal flooding probability of a multi-module high-temperature gas-cooled reactor nuclear power plant is obtained. In the specific calculation, the high-temperature gas-cooled reactor can be calculated based on the pipe rupture data of the pressurized water reactor that has been modified for the applicability of the high-temperature gas-cooled reactor to obtain its flooding frequency.

[0064] S4. Execute the construction of the flooding PSA model to obtain the overall flooding risk of the multi-module high-temperature gas-cooled reactor nuclear power plant.

[0065] The flooding PSA model in this application includes flooding initiating events, event tree models and fault tree models.

[0066] A flooding initiation event refers to an event that causes disturbances in a multi-module high-temperature gas-cooled reactor nuclear power plant and may lead to a serious nuclear accident. Whether the event can cause a serious nuclear accident depends on whether the various mitigation systems of the multi-module high-temperature gas-cooled reactor nuclear power plant can operate successfully. Since each unit of a traditional pressurized water reactor multi-module high-temperature gas-cooled reactor nuclear power plant has only one reactor, the flooding initiation event in the traditional flooding PSA model is only for a single reactor, and cannot handle the situation where flooding initiation events occur simultaneously in multiple modular reactors.

[0067] The event tree model is used to reflect the accident process after the flooding initiating event occurs, that is, the process of each mitigation system of a multi-module high-temperature gas-cooled reactor nuclear power plant being put into use to perform the mitigation function and the final consequences of the accident. The traditional flooding PSA model can only reflect the accident process of one reactor. In the multi-module reactor event tree model established by the traditional method, each module reactor is independent of each other. However, in fact, there is a system function correlation between different module reactors in a high-temperature gas-cooled reactor multi-module high-temperature gas-cooled reactor nuclear power plant, that is, the same system may serve multiple reactor modules at the same time, and the failure of one system will affect the accident process of multiple reactor modules at the same time. The traditional flooding PSA model cannot model this feature.

[0068] The fault tree model is used to reflect the reliability characteristics of the system, that is, how the failure of the equipment leads to the failure of the system. The traditional flooded PSA model takes into account common cause failures, that is, the same equipment in multiple redundant columns of the system fails simultaneously due to the same reason; but the high-temperature gas-cooled reactor has double common cause failures, that is, there is single module common cause failure between the redundant columns of the single module stack, and there are also multi-module common cause failures between different module stacks. The traditional flooded PSA model cannot reflect the latter (multi-module common cause failure) and cannot solve the problem of double common cause failures.

[0069] Based on the above, the steps for constructing the flooding PSA model in this application include the following: Figure 2 As shown:

[0070] S41. Construct multi-module flooding initiating events and multi-module event sequences.

[0071] The above-mentioned multi-module flooding initiating events and multi-module event sequences can reflect the accident process after the flooding initiating events occur simultaneously in multiple module reactors.

[0072] S42. Establish a multi-module shared system model based on the multi-module event sequence.

[0073] Based on the traditional event tree modeling method, a model of a multi-module shared system is established, and the following processing methods are used in the model to enable the model to reflect the system correlation between multiple module stacks: when the design capacity of the multi-module shared system can meet the simultaneous use of multiple module stacks, the system is called simultaneously in the accident process of multiple module stacks in the model; when the design capacity of the multi-module shared system can meet the simultaneous use of multiple module stacks, but the system success criteria are different, boundary conditions are set to simulate the different success criteria when different module stacks call the system; when the design capacity of the multi-module shared system cannot meet the simultaneous use of multiple module stacks, the system call logic is added to the multi-module fault tree model to simulate the situation that multiple stacks cannot call the system simultaneously in the multi-module accident process.

[0074] S43. Set up single-module common cause groups and multi-module high-order common cause basic events in the model.

[0075] That is, a single-module common cause group and a multi-module high-order common cause basic event are set in the above multi-module common system model, thereby obtaining a flooded PSA model, which is used to simulate the double common cause failure of a multi-module stack. Among them, the single-module common cause group reflects the common cause failure between multiple redundant columns of a single module stack, and the high-order common cause basic event reflects the common cause failure between multiple module stacks.

[0076] It can be seen from the above technical scheme that this embodiment provides a method for probabilistic safety analysis of internal flooding of a multi-module high-temperature gas-cooled reactor nuclear power plant. The method is applied to electronic equipment, specifically, based on multiple parameters of the multi-module high-temperature gas-cooled reactor nuclear power plant, flooding zoning, flooding source identification and SSC identification are performed to obtain multiple flooding feature identification results; based on multiple flooding feature identification results, flooding scenario analysis and flooding frequency analysis are performed on the multi-module high-temperature gas-cooled reactor nuclear power plant to obtain flooding impact results and flooding frequency results; based on the flooding impact results and flooding frequency results, a flooding PSA model is constructed, and the internal flooding risk results of the multi-module high-temperature gas-cooled reactor nuclear power plant are obtained by quantitative modeling. This scheme naturally includes multi-module technical elements, so it is possible to implement internal flooding probabilistic safety analysis on the design characteristics of the high-temperature gas-cooled reactor multi-module high-temperature gas-cooled reactor nuclear power plant.

[0077] The flow chart and block diagram in the accompanying drawings illustrate the possible architecture, function and operation of the system, method and computer program product according to various embodiments of the present disclosure. In this regard, each square box in the flow chart or block diagram can represent a module, a program segment or a part of a code, and the module, the program segment or a part of the code contains one or more executable instructions for realizing the specified logical function. It should also be noted that in some implementations as replacements, the functions marked in the square box can also occur in a sequence different from that marked in the accompanying drawings. For example, two square boxes represented in succession can actually be executed substantially in parallel, and they can sometimes be executed in the opposite order, depending on the functions involved. It should also be noted that each square box in the block diagram and / or flow chart, and the combination of the square boxes in the block diagram and / or flow chart can be implemented with a dedicated hardware-based system that performs a specified function or operation, or can be implemented with a combination of dedicated hardware and computer instructions.

[0078] Although operations are depicted in a particular order, this should not be understood as requiring that the operations be performed in the particular order shown or in a sequential order.Multitasking and parallel processing may be advantageous under certain circumstances.

[0079] It should be understood that the various steps described in the method embodiments of the present disclosure may be performed in different orders and / or in parallel. In addition, the method embodiments may include additional steps and / or omit the steps shown. The scope of the present disclosure is not limited in this respect.

[0080] Computer program code for performing the operations of the present disclosure may be written in one or more programming languages ​​or a combination thereof, including, but not limited to, object-oriented programming languages, such as Java, Smalltalk, C++, and conventional procedural programming languages, such as C or similar programming languages. The program code may be executed entirely on the user's computer, partially on the user's computer, as a separate software package, partially on the user's computer and partially on a remote computer, or entirely on a remote computer or server. In cases involving a remote computer, the remote computer may be connected to the user's computer through any type of network, including a local area network (LAN) or a wide area network (WAN), or may be connected to an external computer.

[0081] Figure 3 It is a block diagram of an internal flooding probabilistic safety analysis device for a multi-module high-temperature gas-cooled reactor nuclear power plant according to an embodiment of the present application.

[0082] like Figure 3 As shown, the internal flooding probability safety analysis device of this embodiment is applied to electronic equipment, and is used to analyze and calculate the internal flooding probability of a multi-module high-temperature gas-cooled reactor nuclear power plant. The electronic equipment here can be understood as a computer, server or cloud platform with data computing and information processing capabilities. The internal flooding probability analysis device includes a qualitative analysis and identification processing module 10, a PSA modeling scenario analysis module 20, a quantitative assessment and analysis execution module 30 and a model building module 40.

[0083] The qualitative analysis and identification processing module is used to perform multiple analysis processes on the acquired multiple parameters.

[0084] The multiple parameters here refer to the parameters collected from a multi-module high-temperature gas-cooled reactor nuclear power plant equipped with a high-temperature gas-cooled reactor. On this basis, the multiple parameters are divided into flooding zones, flooding sources are identified, and SSC is identified, thereby obtaining multiple flooding feature identification results. This module includes a first identification unit, a second identification unit, and a third identification unit.

[0085] The first identification unit is used to divide the flooding partitions according to the plant design information of the multi-module high temperature gas-cooled reactor nuclear power plant and based on the physical division between different modules of the multi-module high temperature gas-cooled reactor nuclear power plant, and identify the common mode failure points according to the flooding partitions.

[0086] A flooding partition is a physical object and the smallest unit for flooding analysis. A unit of a high-temperature gas-cooled reactor multi-module high-temperature gas-cooled reactor nuclear power plant is configured with multiple reactor modules. Flooding events in certain flooding partitions will affect multiple reactor modules at the same time. Such flooding partitions are called multi-module reactor common mode failure points, i.e., common mode failure points in this application.

[0087] The second identification unit is used to perform SSC identification on a multi-module high temperature gas-cooled reactor nuclear power plant to obtain an SSC identification result;

[0088] SSC refers to the structures, systems and equipment in a multi-module high temperature gas-cooled reactor nuclear power plant, and the failure impact of SSC and the liquid system of a multi-module high temperature gas-cooled reactor nuclear power plant is considered in the identification process, whether it is a single module, dual stack or multiple modules. In the process of SSC identification, first determine whether the equipment will fail due to flooding; then determine whether the failure of the corresponding equipment due to flooding will lead to a flooding initiation event in a multi-module high temperature gas-cooled reactor nuclear power plant, or whether it will affect the accident mitigation function of a multi-module high temperature gas-cooled reactor nuclear power plant; further, when determining whether the failure of the corresponding equipment due to flooding will lead to a flooding initiation event or affect the mitigation function, whether it will cause a flooding initiation event in multiple reactor modules, and whether it will cause the accident mitigation function of multiple reactor modules to be affected.

[0089] The SSC identification results mainly include the SSC list. The SSC list contains all the equipment identified by the SSC and the flooding zone where each equipment is located; the flooding failure impact of each equipment in the SSC list, including the flooding initiating event caused by the flooding, the mitigation function, and which reactor modules are affected.

[0090] The third identification unit is used to identify the flooding source based on the SSC identification result to obtain the flooding source identification result. Specifically, the flooding source identification includes flooding source screening, flooding source feature identification and flooding source location identification.

[0091] Water flooding source screening is to screen out SSCs containing liquid (including but not limited to water) from all SSCs in a multi-module high-temperature gas-cooled reactor nuclear power plant, and then screen the water flooding sources based on factors such as the total liquid amount, design flow rate, and design pressure.

[0092] Flooding source feature identification is to determine the leakage flow, total leakage and flooding type (there are three types of flooding: spraying, flooding and major flooding) when flooding occurs at the flooding source based on system design parameters, determine the upstream and downstream boundaries of the flooding source, determine the impact of the failure of the flooding source system function on the flooding initiation event and mitigation function of the power plant, and further determine which reactor modules are affected by the failure of the flooding source system function.

[0093] The flood source location identification is to determine the flood zone where the flood source is located and the characteristics of the flood source in each flood zone based on the pipeline layout drawing of the flood source system. The characteristics of the same flood source system in different flood zones may be different.

[0094] The final analysis results include the classification of the multi-module impacts of SSC and flooding sources. Taking a 600MW high-temperature gas-cooled reactor multi-module high-temperature gas-cooled reactor nuclear power plant as an example, the unit has a total of 6 reactor modules. The classification results include affecting reactor module No. 1, affecting reactor module No. 2, affecting reactor module No. 3, affecting reactor module No. 4, affecting reactor module No. 5 and affecting reactor module No. 6, and also include affecting reactor modules No. 1 and 2 at the same time, affecting reactor modules No. 3 and 4 at the same time, affecting reactor modules No. 5 and 6 at the same time, affecting reactor modules No. 1, 2 and 3 at the same time, affecting reactor modules No. 4, 5 and 6 at the same time, and affecting all 6 reactor modules at the same time.

[0095] The PSA modeling scenario analysis module is used to conduct flooding scenario analysis on a multi-module high-temperature gas-cooled reactor nuclear power plant based on multiple flooding feature identification results.

[0096] Based on the above multiple flood feature identification results, flood scenario analysis is carried out, that is, the single-module, dual-stack and multi-module flood initiating events and the impact on system functions caused by internal flooding are analyzed. The flood scenario refers to the process and result of the flooding event. The analysis method is to calculate the spray range, spread range and flood height of the flood according to the characteristics of the flood source (leakage flow, total leakage), and finally determine which equipment is affected by the flood. Then, based on the impact of equipment flooding failure obtained in the previous analysis steps, determine the final impact of the flood scenario, as well as the flood initiating events caused by the flood and the affected mitigation functions.

[0097] The quantitative assessment and analysis execution module is used to process the flooding impact results based on the flooding PSA model.

[0098] By processing multiple flooding impact results, the internal flooding probability of a multi-module high-temperature gas-cooled reactor nuclear power plant is obtained. In specific calculations, the high-temperature gas-cooled reactor can be calculated based on the pipe rupture data of the pressurized water reactor that has undergone applicability modification to the high-temperature gas-cooled reactor to obtain its flooding probability.

[0099] The model building module is used to execute the construction of the flooding PSA model and obtain the overall flooding risk of a multi-module high-temperature gas-cooled reactor nuclear power plant.

[0100] The model building module includes a sequence building unit 41, a model building unit 42 and a model output unit 43. Figure 4 As shown:

[0101] The sequence building module is used to construct multi-module flooding initiating events and multi-module event sequences.

[0102] The above-mentioned multi-module flooding initiating events and multi-module event sequences can reflect the accident process after the flooding initiating events occur simultaneously in multiple module reactors.

[0103] The model building module is used to build a multi-module common system model based on a multi-module event sequence.

[0104] Based on the traditional event tree modeling method, a model of a multi-module shared system is established, and the following processing methods are used in the model to enable the model to reflect the system correlation between multiple module stacks: when the design capacity of the multi-module shared system can meet the simultaneous use of multiple module stacks, the system is called simultaneously in the accident process of multiple module stacks in the model; when the design capacity of the multi-module shared system can meet the simultaneous use of multiple module stacks, but the system success criteria are different, boundary conditions are set to simulate the different success criteria when different module stacks call the system; when the design capacity of the multi-module shared system cannot meet the simultaneous use of multiple module stacks, the system call logic is added to the multi-module fault tree model to simulate the situation that multiple stacks cannot call the system simultaneously in the multi-module accident process.

[0105] The model output module is used to set single-module common cause groups and multi-module high-order common cause basic events in the model.

[0106] That is, a single-module common cause group and a multi-module high-order common cause basic event are set in the above multi-module common system model, thereby obtaining a flooded PSA model, which is used to simulate the double common cause failure of a multi-module stack. Among them, the single-module common cause group reflects the common cause failure between multiple redundant columns of a single module stack, and the high-order common cause basic event reflects the common cause failure between multiple module stacks.

[0107] It can be seen from the above technical scheme that this embodiment provides an internal flooding probabilistic safety analysis device for a multi-module high temperature gas-cooled reactor nuclear power plant, which is applied to electronic equipment, specifically to perform flooding zoning, flooding source identification and SSC identification based on multiple parameters of the multi-module high temperature gas-cooled reactor nuclear power plant, and obtain multiple flooding feature identification results; based on multiple flooding feature identification results, perform flooding scenario analysis and flooding frequency analysis on the multi-module high temperature gas-cooled reactor nuclear power plant, and obtain flooding impact results and flooding frequency results; construct a flooding PSA model based on the flooding impact results and flooding frequency results, and obtain the internal flooding risk results of the multi-module high temperature gas-cooled reactor nuclear power plant through quantitative modeling. This scheme naturally includes multi-module technical elements, so it can implement internal flooding probabilistic safety analysis on the design characteristics of the multi-module high temperature gas-cooled reactor nuclear power plant.

[0108] The units involved in the embodiments described in the present disclosure may be implemented by software or hardware. The name of a unit does not limit the unit itself in some cases. For example, the first acquisition unit may also be described as a "unit for acquiring at least two Internet Protocol addresses".

[0109] The functions described above herein may be performed at least in part by one or more hardware logic components. For example, without limitation, exemplary types of hardware logic components that may be used include: field programmable gate arrays (FPGAs), application specific integrated circuits (ASICs), application specific standard products (ASSPs), systems on chips (SOCs), complex programmable logic devices (CPLDs), and the like.

[0110] Figure 5 A block diagram of an electronic device according to an embodiment of the present application.

[0111] Reference below Figure 5 , which shows a schematic diagram of the structure of an electronic device suitable for implementing the embodiments of the present disclosure. The terminal device in the embodiments of the present disclosure may include, but is not limited to, mobile terminals such as mobile phones, laptop computers, digital broadcast receivers, PDAs (personal digital assistants), PADs (tablet computers), PMPs (portable multimedia players), vehicle-mounted terminals (such as vehicle-mounted navigation terminals), etc., and fixed terminals such as digital TVs, desktop computers, etc. The electronic device is only an example and should not bring any limitation to the functions and scope of use of the embodiments of the present disclosure.

[0112] The electronic device may include a processing device (e.g., a central processing unit, a graphics processing unit, etc.) 601, which can perform various appropriate actions and processes according to a program stored in a read-only memory ROM 602 or a program loaded from an input device 606 into a random access memory RAM 603. In the RAM, various programs and data required for the operation of the electronic device are also stored. The processing device, ROM, and RAM are connected to each other via a bus 604. An input / output (I / O) interface 605 is also connected to the bus 604.

[0113] Typically, the following devices may be connected to the I / O interface: input devices including, for example, a touch screen, a touchpad, a keyboard, a mouse, a camera, a microphone, an accelerometer, a gyroscope, etc.; output devices 607 including, for example, a liquid crystal display (LCD), a speaker, a vibrator, etc.; storage devices 608 including, for example, a magnetic tape, a hard disk, etc.; and communication devices 609. The communication device 609 may allow the electronic device to communicate with other devices wirelessly or by wire to exchange data. Although the figure shows an electronic device with various devices, it should be understood that it is not required to implement or have all the devices shown. More or fewer devices may be implemented or have alternatively.

[0114] This embodiment also provides a computer-readable storage medium embodiment.

[0115] The computer-readable storage medium is applied to an electronic device and carries one or more computer programs. When the one or more computer programs are executed by the electronic device, the electronic device performs flooding zoning, flooding source identification and SSC identification based on multiple parameters of a multi-module high-temperature gas-cooled reactor nuclear power plant, and obtains multiple flooding feature identification results; performs flooding scenario analysis and flooding frequency analysis on the multi-module high-temperature gas-cooled reactor nuclear power plant based on multiple flooding feature identification results, and obtains flooding impact results and flooding frequency results; constructs a flooding PSA model based on the flooding impact results and flooding frequency results, and obtains the internal flooding risk results of the multi-module high-temperature gas-cooled reactor nuclear power plant through quantitative modeling. This solution naturally includes multi-module technical elements, so it can implement internal flooding probabilistic safety analysis on the design characteristics of the high-temperature gas-cooled reactor multi-module high-temperature gas-cooled reactor nuclear power plant.

[0116] It should be noted that the computer-readable medium disclosed above may be a computer-readable signal medium or a computer-readable storage medium or any combination of the above two. The computer-readable storage medium may be, for example, but not limited to, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, device or device, or any combination of the above. More specific examples of computer-readable storage media may include, but are not limited to: an electrical connection with one or more wires, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the above.

[0117] In the present disclosure, a computer-readable storage medium may be any tangible medium containing or storing a program that may be used by or in combination with an instruction execution system, apparatus, or device. In the present disclosure, a computer-readable signal medium may include a data signal propagated in a baseband or as part of a carrier wave, which carries a computer-readable program code. Such propagated data signals may take a variety of forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination of the above. A computer-readable signal medium may also be any computer-readable medium other than a computer-readable storage medium, which may send, propagate, or transmit a program for use by or in combination with an instruction execution system, apparatus, or device. The program code contained on the computer-readable medium may be transmitted using any suitable medium, including but not limited to: wires, optical cables, RF (radio frequency), etc., or any suitable combination of the above.

[0118] The various embodiments in this specification are described in a progressive manner, and each embodiment focuses on the differences from other embodiments. The same or similar parts between the various embodiments can be referenced to each other.

[0119] Although the preferred embodiments of the present invention have been described, those skilled in the art may make additional changes and modifications to these embodiments once they have learned the basic creative concept. Therefore, the appended claims are intended to be interpreted as including the preferred embodiments and all changes and modifications that fall within the scope of the embodiments of the present invention.

[0120] Finally, it should be noted that, in this article, relational terms such as first and second, etc. are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Moreover, the terms "include", "comprise" or any other variants thereof are intended to cover non-exclusive inclusion, so that a process, method, article or terminal device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, article or terminal device. In the absence of further restrictions, the elements defined by the sentence "comprise a ..." do not exclude the existence of other identical elements in the process, method, article or terminal device including the elements.

[0121] The technical solution provided by the present invention is introduced in detail above. Specific examples are used in this article to illustrate the principle and implementation mode of the present invention. The description of the above embodiments is only used to help understand the method of the present invention and its core idea. At the same time, for those skilled in the art, according to the idea of ​​the present invention, there will be changes in the specific implementation mode and application scope. In summary, the content of this specification should not be understood as limiting the present invention.

Claims

1. A method for probabilistic safety analysis of internal flooding of a multi-module high-temperature gas-cooled reactor nuclear power plant, applied to electronic equipment, characterized in that: The internal flooding probabilistic safety analysis method comprises the following steps: Based on multiple parameters of a multi-module high-temperature gas-cooled reactor nuclear power plant, flooding zoning, flooding source identification and SSC identification were performed to obtain multiple flooding feature identification results; Based on the multiple flooding feature identification results, a flooding scenario analysis is performed on the multi-module high temperature gas-cooled reactor nuclear power plant to obtain the flooding impact result; Processing the flooding source identification result to obtain the internal flooding frequency of the multi-module high temperature gas-cooled reactor nuclear power plant; Model construction is performed based on the flooding impact result and the internal flooding frequency to obtain a flooding PSA model for safety analysis of the internal flooding frequency.

2. The internal flooding probabilistic safety analysis method according to claim 1, characterized in that: The method of performing flooding zoning, flooding source identification and SSC identification based on multiple parameters of a multi-module high temperature gas-cooled reactor nuclear power plant to obtain multiple flooding feature identification results includes the following steps: Dividing flooded zones according to building design information of the multi-module high-temperature gas-cooled reactor nuclear power plant, and identifying common mode failure points of the multi-module reactors based on physical separation between different module reactors of the nuclear power plant; Performing SSC identification on the nuclear power plant, finding out the SSC of the flooding initiating event and mitigation facilities affecting the multi-module high temperature gas-cooled reactor nuclear power plant and its impact on the multi-module reactor, and obtaining SSC identification results; The flooding sources of the nuclear power plant are identified, potential flooding sources of the nuclear power plant are screened out, and their flooding characteristics and locations are identified to obtain flooding source identification results.

3. The internal flooding probabilistic safety analysis method according to claim 2, characterized in that: The flooding source identification includes flooding source screening, flooding source feature identification and flooding source location identification.

4. The internal flooding probabilistic safety analysis method according to claim 1, characterized in that: The flooding PSA model includes flooding initiating events, event tree models and fault tree models.

5. The internal flooding probabilistic safety analysis method according to claim 1, characterized in that: The model building is performed based on the flooding impact result and the internal flooding probability to obtain a flooding PSA model for safety analysis of the internal flooding, including the steps of: Constructing a multi-module flooding initiation event and the multi-module event sequence; Establishing a multi-module common system model based on the multi-module event sequence, wherein the multi-module common system model includes system dependencies between multiple module stacks; The single-module common cause group and multi-module high-order common cause basic events are set in the multi-module common system model to obtain the flooding PSA model.

6. An internal flooding probability safety analysis device for a multi-module high-temperature gas-cooled reactor nuclear power plant, applied to electronic equipment, characterized in that: The internal flooding probability analysis device comprises: The qualitative analysis and identification processing module is configured to perform flooding zoning, flooding source identification and SSC identification based on multiple parameters of a multi-module high-temperature gas-cooled reactor nuclear power plant, and obtain multiple flooding feature identification results; A PSA modeling scenario analysis module is configured to perform a flooding scenario analysis on the multi-module high temperature gas-cooled reactor nuclear power plant based on the multiple flooding feature identification results to obtain the flooding impact result; A quantitative assessment and analysis execution module is configured to process the flooding source identification result to obtain the internal flooding frequency of the multi-module high temperature gas-cooled reactor nuclear power plant; The model building module is configured to perform model building based on the flooding impact result and the internal flooding frequency to obtain a flooding PSA model for safety analysis of the internal flooding frequency.

7. The internal flooding probability safety analysis device according to claim 6, characterized in that: The identification processing module includes: A first identification unit is configured to divide flooded zones according to plant design information of the multi-module high temperature gas-cooled reactor nuclear power plant and based on physical divisions between different plant buildings and rooms of the multi-module high temperature gas-cooled reactor nuclear power plant, and identify common mode failure points according to the flooded zones; A second identification unit is configured to perform SSC identification on the multi-module high temperature gas-cooled reactor nuclear power plant to obtain an SSC identification result; The third identification unit is configured to perform flooding source identification and obtain a flooding source identification result.

8. The internal flooding probability safety analysis device according to claim 6, characterized in that: The model building module includes: An event sequence analysis unit configured to construct a multi-module flooding initiating event and the multi-module event sequence; a multi-module correlation analysis unit configured to establish a multi-module common system model based on the multi-module event sequence, wherein the multi-module common system model includes system correlations between a plurality of module stacks; The dual common cause failure analysis unit is configured to set a single module common cause group and a multi-module high-order common cause basic event in the multi-module common system model to obtain the flooding PSA model.

9. An electronic device, characterized in that: The electronic device comprises at least one processor and a memory connected to the processor, wherein: The memory is used to store computer programs or instructions; The processor is used to execute the computer program or instruction so that the electronic device implements the internal flooding probabilistic safety analysis method for a multi-module high-temperature gas-cooled reactor nuclear power plant as described in any one of claims 1 to 5.

10. A computer-readable storage medium, applied to an electronic device, characterized in that: The storage medium carries one or more computer programs, and the one or more computer programs can be executed by the electronic device, so that the electronic device implements the internal flooding probabilistic safety analysis method for a multi-module high-temperature gas-cooled reactor nuclear power plant as described in any one of claims 1 to 5.

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