Initial event identification method and device suitable for new heap type

Abstract

The invention discloses an originating event identification method and device suitable for a new reactor type. The method comprises the following steps: obtaining design information of a new reactor type nuclear power plant; establishing an initial conceptual model corresponding to the new reactor type nuclear power plant according to the design information; based on the initial conceptual model, starting event analysis is carried out, and a starting event list of a new reactor type nuclear power plant design stage is determined; performing iterative design on the initial conceptual model; and according to the concept model after the iterative design, updating the originating event list until the design of the new reactor type nuclear power plant is completed. According to the method and the device, initial event analysis and identification are carried out according to the requirements of the design stage of the new reactor type nuclear power plant, effective initial event identification can be carried out when the design depth is limited, an initial event list can be iteratively perfected along with the design depth of the nuclear power plant, and the safety and the reliability in the design process are ensured.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear power plant safety analysis, and particularly relates to a method and device for identifying initiating events applicable to a new reactor type. Background Art

[0002] An initiating event (IE) is an event that causes a disturbance in a nuclear power plant and has the potential to lead to core damage. Whether the event ultimately leads to core damage depends on what accident prevention and mitigation systems are set in the nuclear power plant design and whether each system can operate successfully. The purpose of identifying initiating events is to find out as completely as possible the initiating events to be evaluated, so as to facilitate subsequent nuclear power plant design and probabilistic safety analysis (PSA). The initiating event list is closely related to the system settings of the nuclear power plant. The design of nuclear power plants with mature reactor types has been relatively fixed. Even for newly built power plants using mature designs, the content of their initiating event lists will not change significantly compared with reference power plants. For such nuclear power plants, the methods for identifying initiating events usually include: engineering evaluation, referring to previous initiating event lists, deductive analysis, and operating experience feedback, etc.

[0003] Among them, the engineering evaluation method requires a systematic review of each system (systems required for operation and safety) and main components of a nuclear power plant to identify whether any failure modes (operation failures, misoperations, ruptures, fractures, collapses, etc.) of these systems and components will directly or in combination with other faults cause core damage. This method requires a relatively detailed system design plan as input, so it is only applicable to designs with a certain foundation or reference plan. Referring to the initiating events of similar nuclear power plants helps obtain a relatively complete list of initiating events, but the applicability of each initiating event in the list to the newly designed power plant needs to be analyzed one by one. This method can be used in the design stage, but the initiating events related to the special design of the power plant from which the list is sourced should be excluded, and the list should be supplemented according to the characteristics of the newly designed power plant. The deductive analysis method takes core damage as the top event and, in a way similar to a fault tree, gradually decomposes it logically from the top event into different categories of events that may lead to this consequence, and finally selects the initiating events from each event at the bottom layer of this logic diagram. When identifying, verifying, and supplementing initiating events through this method, it is necessary to consider the safety functions that must be ensured for the nuclear power plant, the systems and equipment required to perform the functions, and conduct analysis layer by layer at different levels. It can be gradually carried out according to the depth and content of the existing design plan, so there are also certain requirements for the design depth of the newly designed power plant. Identifying initiating events through feedback from operating experience requires consulting the operating history of the nuclear power plant being analyzed (if any) and the operating history of similar nuclear power plants to find out the events that need to be added to the list of initiating events. At the same time, on-site interviews with the operating personnel, maintenance personnel, and safety engineers of the nuclear power plant can also be conducted to avoid omitting initiating events. This approach plays a role in supplementing and improving the initiating events. This method can be used for the design of improved power plants with reference power plants, but its applicability to newly designed power plants is poor; at the same time, although this method may discover common-cause initiating events, it is difficult to discover low-frequency events.

[0004] For nuclear power plants of new reactor types, due to the lack of reference power plants and the fact that how to set up various systems has not been clearly defined in the early stage of the design stage, the use of the above various methods in the early stage of the design stage will be greatly restricted.

[0005] The existing patent CN113887886A discloses a method for identifying an un-fused design extended operating condition list based on risk importance. The method includes: establishing a probabilistic safety analysis model for design extended operating condition analysis; establishing consequence analysis cases according to the initiating event categories; establishing system event groups in the probabilistic safety analysis model to identify the systems to which the basic events in the probabilistic safety analysis belong; calculating the quantitative results of each consequence case and the importance values of each system event group in each consequence case; calculating the possibility of superposing the failures of each system after the occurrence of each initiating event through the quantitative results of each consequence case and the importance values of each system event group; screening the cases of superposing the failures of each system by each initiating event according to the occurrence possibility, and grouping them according to the grouping characteristics of the design extended operating conditions, and finally obtaining the design extended operating condition list. It can be seen from the above that the scheme does not involve the relevant content of initiating event identification.

[0006] The existing patent CN102841600A discloses an analysis method for accident safety analysis of a nuclear fuel reprocessing plant. This scheme conducts initiating event identification for a mature reprocessing plant, mainly including the following steps: selecting a specific site as the research object, and based on this, using the FMEA method to identify its initiating events, conducting risk analysis on the event sequences that may be caused by the initiating events, and then through the risk evaluation and grading method, and making an engineering judgment on the grading results, selecting unique and representative accidents to finally determine the design basis accidents and severe accidents of the nuclear fuel reprocessing plant.

[0007] To sum up, the above two existing patents do not solve the problem that the existing technology's initiating event identification method depends on the design depth of nuclear power plants and is not applicable to new reactor type nuclear power plants in the initial design stage. Summary of the Invention

[0008] Based on the above technical problems, the present invention proposes an initiating event identification method and device applicable to new reactor types, which solves the problem that the existing technology's initiating event identification method depends on the design depth of nuclear power plants and is not applicable to new reactor type nuclear power plants in the initial design stage.

[0009] To achieve the above object, the present invention proposes an initiating event identification method applicable to new reactor types.

[0010] An initiating event identification method applicable to new reactor types includes:

[0011] Obtaining the design information of a new reactor type nuclear power plant;

[0012] Establishing an initial conceptual model corresponding to the new reactor type nuclear power plant according to the design information;

[0013] Conducting initiating event analysis based on the initial conceptual model to determine the initiating event list in the design stage of the new reactor type nuclear power plant;

[0014] Iteratively design the initial conceptual model;

[0015] Update the list of initiating events according to the conceptual model after iterative design until the design of the new reactor type nuclear power plant is completed.

[0016] Furthermore, the design information of the new reactor type nuclear power plant includes: a combination of one or more pieces of information such as the design purpose, usage scenario, fuel type, and coolant type of the new reactor type nuclear power plant.

[0017] Furthermore, establish the initial conceptual model corresponding to the new reactor type nuclear power plant according to the design information, including:

[0018] Establish the initial conceptual model corresponding to the new reactor type nuclear power plant in the form of a process flow diagram according to the design information.

[0019] Furthermore, conduct an initiating event analysis based on the initial conceptual model to determine the list of initiating events in the design stage of the new reactor type nuclear power plant, including:

[0020] Identify the production systems in the initial conceptual model and analyze the functions and the impacts of function failures of each production system;

[0021] Judge whether there are potential initiating events according to the impacts of function failures;

[0022] If there are potential initiating events, analyze the failure causes of the functions to determine the list of initiating events in the design stage of the new reactor type nuclear power plant.

[0023] Furthermore, analyze the failure causes of the functions to determine the list of initiating events in the design stage of the new reactor type nuclear power plant, including:

[0024] Use logical analysis methods to analyze the failure causes of the functions to determine the list of initiating events in the design stage of the new reactor type nuclear power plant. The logical analysis methods include fault tree analysis.

[0025] Furthermore, use logical analysis methods to analyze the failure causes of the functions to determine the list of initiating events in the design stage of the new reactor type nuclear power plant, including:

[0026] Use fault tree analysis to conduct logical analysis on the failure causes of the functions;

[0027] Screen and merge the potential initiating events according to the logical analysis results to determine the list of initiating events in the design stage of the new reactor type nuclear power plant.

[0028] Further, the production system in the initial conceptual model includes: a core that generates energy, a closed primary loop, a steam generator that generates steam, a closed secondary loop, and a steam turbine generator that generates electricity.

[0029] Further, the functions corresponding to the core that generates energy and the closed primary loop include generating energy through fission reactions and transferring energy to the secondary loop. The corresponding functional failure impacts include production interruption and / or core safety challenges; the functions corresponding to the steam generator that generates steam and the closed secondary loop include transferring energy to the steam turbine. The corresponding functional failure impacts include production interruption and / or core safety challenges; the functions corresponding to the steam turbine generator that generates electricity include converting the energy of the secondary loop into electrical energy. The corresponding functional failure impacts include production interruption and / or core safety challenges.

[0030] Further, a logical analysis is performed on the functional failure of transferring energy to the secondary loop, and the identified list of initiating events is a reactor vessel rupture, a main pump rupture, a primary side rupture of the steam generator, a primary loop pipe rupture, and a loss of main pump flow.

[0031] Further, iterative design is performed on the initial conceptual model, including: adding a primary loop coolant inventory regulation, pressure control, and protection system, and / or an additional heat removal system, and / or a secondary loop flow control, pressure control, and protection system on the basis of the initial conceptual model.

[0032] To achieve the above object, the present invention proposes an initiating event identification device applicable to a new reactor type.

[0033] An initiating event identification device applicable to a new reactor type includes:

[0034] An acquisition module, configured to acquire the design information of a new reactor type nuclear power plant;

[0035] A building module, configured to build an initial conceptual model corresponding to the new reactor type nuclear power plant according to the design information;

[0036] A determination module, configured to perform initiating event analysis based on the initial conceptual model to determine the list of initiating events in the design stage of the new reactor type nuclear power plant;

[0037] An iteration module, configured to perform iterative design on the initial conceptual model;

[0038] An update module, configured to update the list of initiating events according to the iteratively designed conceptual model until the design of the new reactor type nuclear power plant is completed.

[0039] Further, the design information of the new reactor type nuclear power plant includes a combination of one or more pieces of information such as the design purpose, usage scenario, fuel type, and coolant type of the new reactor type nuclear power plant.

[0040] Further, a building module is configured to:

[0041] Build an initial conceptual model corresponding to the new reactor type nuclear power plant in the form of a process flow diagram according to the design information.

[0042] Further, a determination module is configured to:

[0043] Identify the production systems in the initial conceptual model, and analyze the functions of each production system and the impacts of function failures;

[0044] Judge whether there is a potential initiating event according to the impact of function failure;

[0045] If there is a potential initiating event, analyze the failure causes of the functions to determine the list of initiating events in the design stage of the new reactor type nuclear power plant.

[0046] Further, the determination module is also configured to:

[0047] Use a logical analysis method to analyze the failure causes of the functions to determine the list of initiating events in the design stage of the new reactor type nuclear power plant, and the logical analysis method includes the fault tree analysis method.

[0048] Further, use a logical analysis method to analyze the failure causes of the functions to determine the list of initiating events in the design stage of the new reactor type nuclear power plant, including:

[0049] Use the fault tree analysis method to conduct a logical analysis of the failure causes of the functions;

[0050] Screen and merge potential initiating events according to the logical analysis results to determine the list of initiating events in the design stage of the new reactor type nuclear power plant.

[0051] Based on the above technical solutions, the present invention has at least the following beneficial effects:

[0052] 1. The present invention proposes to carry out initiating event analysis based on the initial conceptual model, determine the list of initiating events in the design stage of the new reactor type nuclear power plant, and update the list of initiating events as the initial conceptual model is iteratively designed until the design of the new reactor type nuclear power plant is completed. The initiating event analysis and identification carried out according to the requirements of the design stage of the new reactor type nuclear power plant can ensure effective initiating event identification even when the design depth is limited, and can also iteratively improve the list of initiating events as the design depth of the nuclear power plant increases, ensuring safety and reliability during the design process.

[0053] 2. The present invention proposes to use the fault tree analysis method to conduct a logical analysis of the failure causes of the functions of the production systems in the initial conceptual model to determine the corresponding list of initiating events. This solution can reduce the time for fault risk analysis and identify and solve potential safety problems at an early stage of the design stage. Brief Description of the Drawings

[0054] The accompanying drawings forming a part of this invention are used to provide a further understanding of the invention. The schematic embodiments and descriptions thereof of the invention are used to explain the invention and shall not unduly limit the invention. In the drawings:

[0055] Figure 1 is a flowchart of a method for identifying initiating events applicable to a new reactor type according to an embodiment of the present invention;

[0056] Figure 2 is a flow diagram of a conceptual model established according to an embodiment of the present invention;

[0057] Figure 3 is a schematic diagram of logical analysis using the fault tree analysis method according to an embodiment of the present invention;

[0058] Figure 4 is a schematic diagram of the conceptual model after iterative design according to an embodiment of the present invention;

[0059] Figure 5 is a schematic diagram of logical analysis based on the conceptual model after iterative design according to an embodiment of the present invention;

[0060] Figure 6 is a schematic diagram of a device for identifying initiating events applicable to a new reactor type according to an embodiment of the present invention.

[0061] Among them, the above-mentioned drawings include the following reference numerals:

[0062] 1, reactor core; 2, steam generator; 3, main pump; 4, high-pressure heating; 5, main feed water pump; 6, low-pressure heating; 7, condensate pump; 8, deaerator; 9, condenser; 10, high-pressure cylinder; 11, steam-water separation and reheating; 12, low-pressure cylinder; 13, generator; 14, pressurizer; 15, primary coolant inventory regulation pipeline; 16, main feed water flow control valve; 17, safety valve; 18, atmosphere valve; 100, primary production system; 200, secondary production system; 300, primary coolant inventory regulation, pressure control and protection system; 400, additional heat removal system; 500, secondary flow control, pressure control and protection system. Detailed Description of the Embodiments

[0063] It should be noted that, without conflict, the embodiments and features in the embodiments of the present invention may be combined with each other. The present invention will be described in detail below with reference to the drawings and in combination with the embodiments.

[0064] The present invention will be further described in detail below with reference to specific embodiments, and these embodiments should not be construed as limiting the scope claimed by the present invention.

[0065] Embodiment

[0066] To solve the problem that the existing method for identifying initiating events depends on the design depth of nuclear power plants and is not applicable to new reactor type nuclear power plants in the initial design stage, the present invention proposes a method and device for identifying initiating events applicable to new reactor types.

[0067] To achieve the above object, the present invention proposes a method for identifying initiating events applicable to new reactor types.

[0068] As Figure 1 shown in the flowchart of a method for identifying initiating events applicable to new reactor types according to an embodiment of the present invention, as Figure 1 shown, the method includes the following steps:

[0069] S1. Obtain the design information of the new reactor type nuclear power plant.

[0070] For a newly designed nuclear power plant, neither the production system in normal operation nor the system dedicated to accident response has been clearly defined, but there is still some information that needs to be clarified, including: a combination of one or more of the design purpose, usage scenario, possible fuel type, and coolant type of the new reactor type nuclear power plant. The clarification of this information helps to establish a conceptual model and carry out subsequent design work.

[0071] In this embodiment, the obtained design information includes the design purpose, usage scenario, and coolant type of the new reactor type nuclear power plant. Specifically, the nuclear power plant is designed to provide civilian electricity, is intended to be connected to a large power grid, and light water is considered as the moderator and coolant.

[0072] S2. Establish an initial conceptual model corresponding to the new reactor type nuclear power plant according to the design information.

[0073] Considering that the production system directly serves the production function and design goal of the new reactor type nuclear power plant, and the accident response system serves the safety of the production function, in principle, the design of the production system should be earlier than the design of the accident response system. Before the concept or initial design of the production system is established, the identification of initiating events lacks the most basic analysis object. For a nuclear power plant in the early stage of the design phase, although the design of its production system may still be unclear in terms of specific form and details, its overall concept should be relatively easy to clarify, such as whether it is necessary to rely on the phase change of the medium during the process of energy transfer and conversion. With the existing design information and the concept of the production system, a conceptual model can be established in the form of a process flow diagram.

[0074] In this embodiment, based on the existing design information obtained in step S1, further consider using a pressurized water reactor design for the time being, that is, the energy transfer and conversion process of "a core that generates energy and a closed primary loop, a steam generator that generates steam and a closed secondary loop, and a steam turbine generator that generates electricity". For this process and the most important production system therein, a conceptual model established in the form of a flow diagram is as Figure 2 shown. The Figure 2 includes a primary loop production system 100 and a secondary loop production system 200. The primary loop production system 100 includes a reactor core 1, a steam generator 2, and a main pump 3. The secondary loop production system 200 includes a high-pressure heater 4, a main feed water pump 5, a low-pressure heater 6, a condensate pump 7, a deaerator 8, a condenser 9, a high-pressure cylinder 10, a moisture separator reheater 11, a low-pressure cylinder 12, and a generator 13.

[0075] Figure 2 only contains the most important production system processes, retains the necessary heat sink interfaces, but does not limit the form of the heat sink, nor does it include other support systems and auxiliary systems such as power supply and gas supply, and does not involve systems dedicated to accident response, and is applicable to the early stage of the design phase of a pressurized water reactor nuclear power plant.

[0076] S3. Conduct an initiating event analysis based on the initial conceptual model to determine the list of initiating events in the design phase of the new reactor type nuclear power plant.

[0077] Furthermore, conduct an initiating event analysis based on the initial conceptual model to determine the list of initiating events in the design phase of the new reactor type nuclear power plant, including:

[0078] S301. Identify the production systems in the initial conceptual model and analyze the functions of each production system and the impacts of function failures.

[0079] In this embodiment, in the order from upstream to downstream, the production systems in the initial conceptual model are divided into: a core that generates energy and a closed primary loop, a steam generator that generates steam and a closed secondary loop, and a steam turbine generator that generates electricity. An example of the analysis of the functions of each production system and the impacts of function failures is shown in Table 1.

[0080] Table 1 Example analysis of the functions of each production system in the initial conceptual model and the impacts of function failures

[0081]

[0082]

[0083] As can be seen from Table 1, the functions corresponding to the energy - generating core and the closed primary loop system include generating energy through fission reactions and transferring energy to the secondary loop. The corresponding functional failure impacts include production interruption and / or core safety challenges. The functions corresponding to the steam generator that generates steam and the closed secondary loop system include transferring energy to the steam turbine. The corresponding functional failure impacts include production interruption and / or core safety challenges. The functions corresponding to the steam turbine generator that generates electricity include converting the energy of the secondary loop into electrical energy. The corresponding functional failure impacts include production interruption and / or core safety challenges.

[0084] S302, Determine whether there is a potential initiating event based on the functional failure impact.

[0085] Specifically, in this embodiment, the basis for determining whether there is a potential initiating event is: when the functional failure of the system poses a challenge to the target of concern (such as core safety or continuous production), there is a potential initiating event. As the functional failure impacts of the three systems in Table 1 above all include production interruption and core safety challenges, it is determined that there is a potential initiating event.

[0086] S303, If there is a potential initiating event, analyze the cause of the functional failure to determine the list of initiating events in the design stage of the new reactor type nuclear power plant.

[0087] Generally speaking, analyzing the cause of the functional failure includes: directly analyzing the cause of the functional failure or further analyzing the cause of the functional failure using logical analysis methods. Further, whether to conduct a logical analysis of the cause of the functional failure depends on whether the current analysis level requirements and design depth can support it. Specifically, if only a general understanding of the system function level is currently required, there is no need to conduct an expansion. If a deeper level of understanding is currently required and the design depth supports it, then a logical analysis needs to be conducted, specifically expanding to the subsystem, equipment, or finer levels. For example, in the steam turbine generator production system that generates electricity in Table 1, its corresponding function is to convert the energy of the secondary loop into electrical energy, and the corresponding functional failure impacts include production interruption and / or core safety challenges. Based on its function and functional failure impacts, it can be determined that there is a potential initiating event, but since the generator is already at the equipment level, it can be temporarily not expanded.

[0088] The logical analysis method includes the fault tree analysis method. In a specific embodiment of the present invention, the process of analyzing the cause of the functional failure to determine the list of initiating events in the design stage of the new reactor type nuclear power plant is as follows:

[0089] S3031, Use the fault tree analysis method to conduct a logical analysis of the cause of the functional failure.

[0090] Taking the system function of "transferring energy to the secondary loop" in the energy - generating core and the closed primary loop system in Table 1 as an example, based on its corresponding functions and the impacts of function failures, potential initiating events can be determined, and further logical analysis is required. In this example, the fault tree analysis method is used for logical analysis, and the specific analysis is as shown in Figure 3 as follows. It can be seen from Figure 3 that after analysis, the events that may cause the failure of the system function of "transferring energy to the secondary loop" (i.e., the causes of function failure) may include: a decrease in the inventory of primary coolant, a reduction in the primary coolant flow rate. The events that cause a decrease in the inventory of primary coolant include reactor vessel rupture, main pump rupture, rupture of the primary side of the steam generator, and rupture of the primary loop pipeline. The events that cause a reduction in the primary coolant flow rate include loss of main pump flow.

[0091] S3032, screen and merge potential initiating events according to the results of logical analysis to determine the list of initiating events in the design stage of the new reactor type nuclear power plant.

[0092] According to the results of the logical analysis in the above steps, the list of initiating events corresponding to this production system can be determined as reactor vessel rupture, main pump rupture, rupture of the primary side of the steam generator, rupture of the primary loop pipeline, and loss of main pump flow.

[0093] Some of the initiating events in the results of logical analysis can logically lead to the occurrence of the top event, but there are some initiating events that may not occur or have an extremely low probability of occurrence in reality, or in subsequent designs, targeted measures have been taken to eliminate this event. In the above cases, this initiating event can be considered for screening. Further, although some initiating events are two events, considering that their impacts may be the same or extremely similar, in this case, the two initiating events can be considered for merging into one or a group. Potential initiating events can be screened and merged according to the above screening and merging methods to determine the list of initiating events in the design stage of the new reactor type nuclear power plant.

[0094] S4, perform iterative design on the initial conceptual model.

[0095] As the design work progresses, the specific forms and details of various systems in the nuclear power plant become gradually clear and rich. At this time, the initial conceptual model can be further improved into a more detailed design model. In this embodiment, some systems are added to the nuclear power plant to better maintain the operation of the production system and the safety of the reactor. The conceptual model after iterative design is as shown in Figure 4As shown. Specifically, on the basis of the initial conceptual model, a primary coolant inventory regulation, pressure control and protection system 300, an additional heat removal system 400, and a secondary loop flow control, pressure control and protection system 500 are added. Specifically, the primary coolant inventory regulation, pressure control and protection system 300 includes a pressurizer 14, a safety valve above the pressurizer 14, and a primary water inventory regulation pipeline 15; the secondary loop flow control, pressure control and protection system 500 includes a main feedwater flow control valve 16, a safety valve 17, and an atmospheric valve 18.

[0096] S5. According to the conceptual model after iterative design, update the initiating event list until the design of the new reactor type nuclear power plant is completed.

[0097] This step is relatively similar to the content of the above step S3. Conduct an initiating event analysis based on the conceptual model after iterative design and update the initiating event list. The specific process is as follows: Analyze the functions and the impacts of function failures of each production system in the iterative conceptual model, and then determine potential initiating events based on the functions and the impacts of function failures of each production system and / or conduct a logical analysis of the functions and the impacts of function failures of each production system to determine the initiating event list in the design stage of the new reactor type nuclear power plant. Table 2 shows an example of the analysis of the functions and the impacts of function failures of each production system in the iterative conceptual model in this embodiment.

[0098] Table 2 Example of the analysis of the functions and the impacts of function failures of each production system in the iterative conceptual model

[0099]

[0100]

[0101] As shown in Table 2, the iterative conceptual model includes a core that generates energy, a closed primary loop, and systems connected to the primary loop, etc. (Table 2 only shows the production systems related to the primary loop), and the corresponding system functions include nuclear fission reaction to generate energy, transfer energy to the secondary loop, and reactor heat removal under specific conditions. It can be specifically divided into the following systems: a primary coolant inventory regulation system, a primary loop pressure control and protection system, and an additional heat removal system. For a further logical analysis of the system function of "transferring energy to the secondary loop", see Figure 5 . From Figure 5It can be seen that after iterative update, the events that lead to a reduction in the primary coolant inventory during the fault tree analysis have increased. Specifically, the mis-opening of the pressure protection system, the mis-connection of the additional heat removal system and the occurrence of a rupture or the mis-opening of the pressure protection, and the mis-initiation of the drainage of the coolant inventory regulation system may all lead to a reduction in the primary coolant inventory. Among them, the events that lead to the mis-connection of the additional heat removal system and the occurrence of a rupture or the mis-opening of the pressure protection include: the mis-connection of the additional heat removal system, the occurrence of a rupture in the additional heat removal system or the mis-opening of the pressure protection. The events that lead to the occurrence of a rupture in the additional heat removal system or the mis-opening of the pressure protection include: the rupture of the pipes or equipment in the additional heat removal system, the mis-opening of the pressure protection in the additional heat removal system. The updated list of initiating events includes: the rupture of the reactor vessel, the rupture of the main pump, the rupture of the primary side of the steam generator, the rupture of the primary loop pipes and the loss of main pump flow, the mis-opening of the pressure protection system, the mis-initiation of the drainage of the coolant inventory regulation system, the mis-connection of the additional heat removal system, the rupture of the pipes or equipment in the additional heat removal system, the mis-opening of the pressure protection in the additional heat removal system. Among them, the "mis-opening of the pressure protection system" and the "mis-connection of the additional heat removal system and the mis-opening of the pressure protection in the additional heat removal system" may be considered for merger in the subsequent analysis, and the more serious one of the two is used as a representative.

[0102] To achieve the above object, the present invention proposes an initiating event identification device applicable to a new reactor type.

[0103] As Figure 6 FIG. shows a schematic diagram of an initiating event identification device applicable to a new reactor type according to an embodiment of the present invention. The device includes: an acquisition module 61, a establishment module 62, a determination module 63, an iteration module 64 and an update module 65. The functions of each module will be introduced in detail below.

[0104] The acquisition module 61 is used to acquire the design information of the new reactor type nuclear power plant.

[0105] Further, the design information of the new reactor type nuclear power plant includes: one or a combination of information such as the design purpose, usage scenario, fuel type and coolant type of the new reactor type nuclear power plant.

[0106] The establishment module 62 is used to establish an initial conceptual model corresponding to the new reactor type nuclear power plant according to the design information.

[0107] Further, the establishment module 62 is used for:

[0108] According to the design information, establish an initial conceptual model corresponding to the new reactor type nuclear power plant in the form of a process flow diagram.

[0109] A determination module 63, configured to perform an initiating event analysis based on an initial conceptual model and determine a list of initiating events in the design phase of a new reactor type nuclear power plant.

[0110] Further, the determination module 63 is configured to:

[0111] Identify the production systems in the initial conceptual model and analyze the functions of each production system and the impacts of function failures;

[0112] Judge whether there are potential initiating events according to the impacts of function failures;

[0113] If there are potential initiating events, analyze the failure causes of the functions to determine a list of initiating events in the design phase of the new reactor type nuclear power plant.

[0114] Further, the determination module 63 is further configured to:

[0115] Use a logical analysis method to analyze the failure causes of the functions to determine a list of initiating events in the design phase of the new reactor type nuclear power plant, where the logical analysis method includes a fault tree analysis method.

[0116] Further, use a logical analysis method to analyze the failure causes of the functions to determine a list of initiating events in the design phase of the new reactor type nuclear power plant, including:

[0117] Use the fault tree analysis method to perform a logical analysis on the failure causes of the functions;

[0118] Screen and merge the potential initiating events according to the logical analysis results to determine a list of initiating events in the design phase of the new reactor type nuclear power plant.

[0119] An iteration module 64, configured to perform iterative design on the initial conceptual model.

[0120] An update module 65, configured to update the list of initiating events according to the iteratively designed conceptual model until the design of the new reactor type nuclear power plant is completed.

[0121] It should be understood that the embodiments of an initiating event recognition device applicable to a new reactor type are consistent with the descriptions of the corresponding initiating event recognition method applicable to a new reactor type, so the present embodiment will not be elaborated herein.

[0122] In summary, it can be seen from the above description that the above embodiments of the present invention achieve the following technical effects:

[0123] 1. The present invention proposes to conduct an initiating event analysis based on an initial conceptual model to determine the initiating event list for the design stage of a new reactor type nuclear power plant, and update the initiating event list with the iterative design of the initial conceptual model until the design of the new reactor type nuclear power plant is completed. The initiating event analysis and identification carried out according to the requirements of the design stage of the new reactor type nuclear power plant can ensure effective initiating event identification even when the design depth is limited, and can also iteratively improve the initiating event list with the design depth of the nuclear power plant to ensure safety and reliability during the design process.

[0124] 2. The present invention proposes to use the fault tree analysis method to conduct a logical analysis of the failure causes of the functions of the production system in the initial conceptual model to determine the corresponding initiating event list. This solution can reduce the time for fault risk analysis and identify and solve potential safety problems at an early stage of the design stage.

[0125] The above are only the preferred embodiments of the present invention and are not intended to limit the present invention. For those skilled in the art, the present invention can have various changes and modifications. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention shall be included within the protection scope of the present invention.

[0126] It should be noted that in this article, relational terms such as first and second are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any actual relationship or order between these entities or operations. Moreover, the term "comprising", "including" or any other variation thereof is intended to cover a non-exclusive inclusion, so that a process, method, article or device comprising a series of elements not only includes those elements, but also includes other elements not expressly listed, or elements inherent to such process, method, article or device. Without further limitation, an element defined by the statement "comprising an..." does not exclude the existence of additional identical elements in the process, method, article or device comprising the element.

[0127] The logic and / or steps represented in the flowchart or described in other ways herein, for example, can be considered as a definite sequence list of executable instructions for implementing logical functions, and can be specifically implemented in any computer-readable medium for use by an instruction execution system, apparatus or device (such as a computer-based system, a system including a processor, or other systems that can fetch instructions from the instruction execution system, apparatus or device and execute the instructions), or in combination with these instruction execution systems, apparatus or devices.

[0128] It should be understood that each part of the present invention can be implemented by hardware, software, firmware, or a combination thereof. In the above embodiments, multiple steps or methods can be implemented by software or firmware stored in a memory and executed by a suitable instruction execution system. For example, if implemented by hardware, as in another embodiment, any one or a combination of the following techniques well known in the art can be used: discrete logic circuits having logic gate circuits for implementing logical functions on data signals, application specific integrated circuits having appropriate combinational logic gate circuits, programmable gate arrays (PGAs), field programmable gate arrays (FPGAs), etc.

[0129] It should be noted that in the description of this specification, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples", etc. means that the specific features, structures, materials, or characteristics described in connection with the embodiment or example are included in at least one embodiment or example of the present invention. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials, or characteristics described can be combined in any one or more embodiments or examples in a suitable manner. In addition, without contradiction, those skilled in the art can combine and combine the different embodiments or examples described in this specification and the features of different embodiments or examples.

Claims

1. A method for identifying initiating events applicable to new reactor types, characterized in that: include: Obtain design information for new reactor-type nuclear power plants; Establishing an initial conceptual model corresponding to the new reactor type nuclear power plant according to the design information; Conducting initiating event analysis based on the initial conceptual model to determine the initiating event list for the design phase of the new reactor type nuclear power plant; Iteratively designing the initial concept model; The list of initiating events is updated according to the conceptual model after iterative design until the design of the new reactor type nuclear power plant is completed.

2. The method according to claim 1, characterized in that The design information of the new reactor type nuclear power plant includes: a combination of one or more information of the design purpose, usage scenario, fuel type and coolant type of the new reactor type nuclear power plant.

3. The method according to claim 1, characterized in that An initial conceptual model corresponding to the new reactor type nuclear power plant is established according to the design information, including: Based on the design information, an initial conceptual model corresponding to the new reactor type nuclear power plant is established in the form of a flow chart.

4. The method according to claim 1, characterized in that: Based on the initial conceptual model, an initiating event analysis is carried out to determine the initiating event list for the design phase of the new reactor type nuclear power plant, including: Identify the production systems in the initial conceptual model and analyze the functions of each production system and the impact of functional failure; Determine whether there is a potential initiating event based on the impact of the functional failure; If there are potential initiating events, the failure causes of the functions are analyzed and a list of initiating events for the design phase of the new reactor type nuclear power plant is determined.

5. The method according to claim 4, characterized in that Analyze the failure causes of the functions and determine the list of initiating events in the design phase of the new reactor type nuclear power plant, including: The failure causes of the functions are analyzed by using a logic analysis method to determine a list of initiating events in the design phase of the new reactor type nuclear power plant, wherein the logic analysis method includes a fault tree analysis method.

6. The method according to claim 5, characterized in that The failure causes of the functions are analyzed by using a logical analysis method to determine a list of initiating events in the design phase of the new reactor type nuclear power plant, including: Perform a logical analysis of the failure causes of the functions described using the fault tree analysis method; Potential initiating events are screened and merged according to the results of the logic analysis to determine the initiating event list for the design phase of the new reactor type nuclear power plant.

7. The method according to claim 4, characterized in that The production system in the initial conceptual model includes: a core and a closed primary circuit for generating energy, a steam generator and a closed secondary circuit for generating steam, and a steam turbine generator for generating electricity.

8. The method according to claim 7, characterized in that The functions corresponding to the energy-generating core and the closed primary loop include fission reaction energy production and energy transfer to the secondary loop, and the corresponding functional failure impacts include production interruption and / or core safety challenges; the functions corresponding to the steam generator and the closed secondary loop for generating steam include energy transfer to the steam turbine, and the corresponding functional failure impacts include production interruption and / or core safety challenges; the functions corresponding to the steam turbine generator for generating electricity include converting the secondary loop energy into electrical energy, and the corresponding functional failure impacts include production interruption and / or core safety challenges.

9. The method according to claim 8, characterized in that A logical analysis was performed on the failure of the energy transfer function to the secondary circuit, and the list of initiating events determined was reactor vessel rupture, main pump rupture, steam generator primary side rupture, primary circuit pipeline rupture and main pump flow loss.

10. The method according to any one of claims 7 to 9, characterized in that: The initial conceptual model is iteratively designed, including: adding a primary circuit coolant charge adjustment, pressure control and protection system, and / or an additional heat removal system, and / or a secondary circuit flow control, pressure control and protection system based on the initial conceptual model.

11. An initiating event identification device suitable for a new reactor type, characterized in that: include: An acquisition module is used to obtain design information of a new reactor type nuclear power plant; An establishment module is used to establish an initial conceptual model corresponding to the new reactor type nuclear power plant according to the design information; A determination module, used to carry out initiating event analysis based on the initial conceptual model and determine the initiating event list in the design phase of the new reactor type nuclear power plant; An iteration module, used for iteratively designing the initial concept model; An updating module is used to update the list of initiating events according to the conceptual model after iterative design until the design of the new reactor type nuclear power plant is completed.

12. The device according to claim 11, characterized in that The design information of the new reactor type nuclear power plant includes: a combination of one or more information of the design purpose, usage scenario, fuel type and coolant type of the new reactor type nuclear power plant.

13. The device according to claim 11, characterized in that The establishment module is used to: Based on the design information, an initial conceptual model corresponding to the new reactor type nuclear power plant is established in the form of a flow chart.

14. The device according to claim 11, characterized in that The determining module is used to: Identify the production systems in the initial conceptual model and analyze the functions of each production system and the impact of functional failure; Determine whether there is a potential initiating event based on the impact of the functional failure; If there are potential initiating events, the failure causes of the functions are analyzed and a list of initiating events for the design phase of the new reactor type nuclear power plant is determined.

15. The device according to claim 14, characterized in that The determining module is further used for: The failure causes of the functions are analyzed by using a logic analysis method to determine a list of initiating events in the design phase of the new reactor type nuclear power plant, wherein the logic analysis method includes a fault tree analysis method.

16. The device according to claim 15, characterized in that The failure causes of the functions are analyzed by using a logical analysis method to determine a list of initiating events in the design phase of the new reactor type nuclear power plant, including: Perform a logical analysis of the failure causes of the functions described using the fault tree analysis method; Potential initiating events are screened and merged according to the results of the logic analysis to determine the initiating event list for the design phase of the new reactor type nuclear power plant.

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