Method, system, device and medium for emergency assessment of dry storage spent fuel of nuclear power plant

Abstract

The application provides a kind of nuclear power plant dry storage spent fuel emergency evaluation method, system, equipment and medium, applied to dry nuclear horizontal modular storage system, the dry nuclear horizontal modular storage system includes concrete module and storage container, the method comprises: obtaining the information of natural disaster;According to the type and risk parameter of the natural disaster information of the natural disaster;In response to the risk parameter being higher than the response threshold, the radiation dose of the concrete module is obtained;According to the radiation dose, the effective multiplication coefficient of the storage container is obtained;In response to the effective multiplication coefficient being higher than the effective multiplication coefficient threshold, the storage container transfer operation is executed, can be integrated together by natural disaster risk assessment, radiation dose monitoring and effective multiplication coefficient control, form a complete emergency evaluation and response system, improve the overall efficiency of nuclear power plant in response to disaster.

Description

Technical Field

[0001] This application pertains to the field of spent fuel management, and particularly relates to emergency assessment methods, systems, equipment, and media for dry storage of spent fuel in nuclear power plants. Background Technology

[0002] Dry storage of spent fuel is a technology used in the nuclear energy field for the long-term storage of used nuclear fuel. Compared to traditional wet storage (which stores nuclear fuel in a water pool), dry storage does not require large amounts of water and can more effectively control the release of radioactive materials, thereby reducing environmental and health risks.

[0003] Currently, the commonly used Nuclear Horizontal Modular Storage (NUHOMS) system is a heat dissipation system that transfers the decay heat of spent fuel to the dry storage canister (DSC) through conduction, radiation, and natural convection. The heat is then transferred from the double-walled, welded, sealed storage canister to the surrounding air via cooling channels within the horizontal storage module-hot (HSM-H). However, there is a lack of methods in the relevant technologies for evaluating the availability of NUHOMS systems under extreme weather conditions. Summary of the Invention

[0004] In view of this, embodiments of this application provide a method, system, equipment and medium for emergency assessment of dry storage of spent fuel in nuclear power plants, in order to solve the problem that there is a lack of methods in the prior art for assessing the availability of dry nuclear horizontal modular storage systems under extreme weather conditions.

[0005] A first aspect of this application provides an emergency assessment method for dry storage of spent fuel in a nuclear power plant, applied to a dry nuclear horizontal modular storage system. The dry nuclear horizontal modular storage system includes concrete modules and storage containers. The method includes: acquiring information about natural disasters; acquiring the type and risk parameters of the natural disasters based on the natural disaster information; acquiring the radiation dose of the concrete modules in response to the risk parameters being higher than a response threshold; acquiring the effective multiplication coefficient of the storage containers based on the radiation dose; and performing a transfer operation of the storage containers in response to the effective multiplication coefficient being higher than an effective multiplication coefficient threshold.

[0006] In conjunction with the first aspect, in a first possible implementation of the first aspect, obtaining the effective multiplication coefficient of the storage container based on the radiation dose includes: obtaining the radiation dose and a radiation field model of the storage container; simulating the nuclear reaction process within the storage container based on the radiation field model of the storage container; obtaining the neutron production rate and neutron loss rate based on the nuclear reaction process; and obtaining the effective multiplication coefficient based on the neutron production rate and the neutron loss rate.

[0007] In conjunction with the first aspect, in a second possible implementation of the first aspect, after obtaining the radiation dose of the concrete module, the method further includes: obtaining the degree of damage to the concrete module; obtaining information on damaged components based on the degree of damage; obtaining a repair order for the damaged components based on the information on the damaged components; and repairing the damaged components according to the repair order.

[0008] In conjunction with the first aspect, in a third possible implementation of the first aspect, the method further includes: obtaining the repairability of the damaged component based on the degree of damage; and performing the storage container transfer operation in response to the repairability of the damaged component being lower than a repairability threshold.

[0009] In conjunction with the first aspect, in the fourth possible implementation of the first aspect, the types of natural disasters include typhoons, floods, and earthquakes.

[0010] In conjunction with the first aspect, in the fifth possible implementation of the first aspect, the method further includes: obtaining environmental impact parameters based on the type of the natural disaster and the risk parameters; when the type of the natural disaster is a typhoon, the environmental impact parameter is wind speed; when the type of the natural disaster is a flood, the environmental impact parameter is static water pressure and water flow velocity; when the type of the natural disaster is an earthquake, the environmental impact parameter is horizontal acceleration and vertical acceleration.

[0011] In conjunction with the first aspect, in the sixth possible implementation of the first aspect, when the type of natural disaster is a typhoon, the response threshold is 477 kilometers per hour.

[0012] In conjunction with the first aspect, in the seventh possible implementation of the first aspect, when the type of natural disaster is flood, the response threshold is 15.24 meters of static water pressure and 4.572 meters per second of water flow velocity.

[0013] In conjunction with the first aspect, in the eighth possible implementation of the first aspect, when the type of natural disaster is an earthquake, the response threshold is 0.3g horizontal acceleration and 0.25g vertical acceleration.

[0014] In conjunction with the first aspect, in the ninth possible implementation of the first aspect, the effective proliferation coefficient threshold is 0.95.

[0015] A second aspect of this application provides an emergency assessment system for dry storage of spent fuel in a nuclear power plant, applied to the steps of the method described in the first aspect. The system includes: a disaster information acquisition module for acquiring information about natural disasters; a risk assessment module for acquiring the type and risk parameters of the natural disaster based on the natural disaster information; a radiation dose acquisition module for acquiring the radiation dose of the concrete module in response to the risk parameter being higher than a response threshold; an effective multiplication coefficient acquisition module for acquiring the effective multiplication coefficient of the storage container based on the radiation dose; and an execution module for performing a transfer operation of the storage container in response to the effective multiplication coefficient being higher than an effective multiplication coefficient threshold.

[0016] A third aspect of this application provides a terminal device including a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the computer program to implement the steps of the method as described in any of the first aspects.

[0017] A fourth aspect of this application provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the steps of the method as described in any of the first aspects.

[0018] The beneficial effects of this application embodiment compared with the prior art are: by integrating natural disaster risk assessment, radiation dose monitoring and effective multiplication coefficient control, a complete emergency assessment and response system is formed, which improves the overall efficiency of nuclear power plants in responding to disasters. Attached Figure Description

[0019] To more clearly illustrate the technical solutions in the embodiments of this application, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments of this application. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0020] Figure 1 This is a schematic diagram of the dry nuclear horizontal modular storage system provided in the embodiments of this application;

[0021] Figure 2 This is a schematic diagram of the concrete module provided in an embodiment of this application;

[0022] Figure 3 This is a schematic diagram illustrating the implementation process of the emergency assessment method for dry storage of spent fuel in nuclear power plants provided in the embodiments of this application;

[0023] Figure 4 This is a schematic diagram illustrating the implementation process of the emergency assessment method for dry storage of spent fuel in nuclear power plants provided in the embodiments of this application;

[0024] Figure 5 This is a schematic diagram of the emergency assessment system for dry storage of spent fuel in nuclear power plants provided in the embodiments of this application;

[0025] Figure 6 This is a schematic diagram of the terminal device provided in the embodiments of this application. Detailed Implementation

[0026] In the following description, specific details such as particular system architectures and techniques are set forth for illustrative purposes and not for limitation, in order to provide a thorough understanding of the embodiments of this application. However, those skilled in the art will understand that this application may also be implemented in other embodiments without these specific details. In other instances, detailed descriptions of well-known systems, apparatuses, circuits, and methods have been omitted so as not to obscure the description of this application with unnecessary detail.

[0027] Currently, the commonly used Nuclear Horizontal Modular Storage (NUHOMS) system is a heat dissipation system that transfers the decay heat of spent fuel to the dry storage canister (DSC) through conduction, radiation, and natural convection. The heat is then transferred from the double-layered welded and sealed storage canister to the surrounding air via cooling channels in the horizontal storage module-hot (HSM-H). Related technologies include methods for evaluating the availability of NUHOMS systems under extreme weather conditions. In particular, extreme weather events such as typhoons, earthquakes, and floods may cause displacement or deformation of the concrete modules, leading to deformation of the storage canister. Furthermore, extreme weather can affect the shielding function of the NUHOMS system, resulting in increased radiation dose.

[0028] The emergency assessment method, system, equipment, and media for dry storage of spent fuel in nuclear power plants provided in this application have significant beneficial effects in the field of dry nuclear horizontal modular storage systems. By integrating natural disaster risk assessment, radiation dose monitoring, and effective multiplication factor control, a complete emergency assessment and response system is formed, improving the overall efficiency of nuclear power plants in responding to disasters.

[0029] To illustrate the technical solution described in this application, specific embodiments are provided below.

[0030] Figure 1 This is a schematic diagram of the dry nuclear horizontal modular storage system 10 provided in an embodiment of this application, as shown below. Figure 1 As shown, the dry nuclear horizontal modular storage system 10 includes a first concrete module 101, a second concrete module 102, a third concrete module 103, and a fourth concrete module 104. It is understood that the distribution and arrangement of the concrete modules within the system are based on considerations of safety and storage efficiency, ensuring that the system can operate stably under different conditions.

[0031] Please refer to the following: Figure 2 , Figure 2 This is a schematic diagram of the concrete module 100 provided in an embodiment of this application. Figure 2 As shown, the concrete module 100 includes at least a cooling channel 110 and a storage container 120.

[0032] It is understood that the number of concrete modules included in the dry nuclear horizontal modular storage system 10 in this application embodiment is merely an example. Those skilled in the art can design more or fewer concrete modules according to actual conditions, and this application does not impose any restrictions on this.

[0033] Understandably, the cooling channel 110 is designed to transfer the decay heat of spent fuel through natural convection, radiation, and other means, thereby maintaining a stable temperature in the dry nuclear horizontal modular storage system 10. The storage container 120 holds the spent fuel, ensuring its safe storage. The rational design of the layout and structure of these core components enables the entire dry nuclear horizontal modular storage system 10 to effectively dissipate heat.

[0034] Figure 3 This is a schematic diagram illustrating the implementation process of the emergency assessment method for dry storage of spent fuel in nuclear power plants provided in this application embodiment. Figure 3 As shown, the emergency assessment method for dry storage of spent fuel in nuclear power plants includes at least the following steps: S100: Obtain information on natural disasters; S200: Obtain the type and risk parameters of natural disasters based on the natural disaster information; S300: In response to the risk parameters being higher than the response threshold, obtain the radiation dose of the concrete module; S400: Obtain the effective multiplication coefficient of the storage container based on the radiation dose; S500: In response to the effective multiplication coefficient being higher than the effective multiplication coefficient threshold, perform a storage container transfer operation.

[0035] The emergency assessment method for dry storage of spent fuel in nuclear power plants provided in this application embodiment is applicable to, for example... Figure 1 The dry nuclear horizontal modular storage system 10 shown is Figure 2The concrete module 100 shown is included in the dry nuclear horizontal modular storage system 10, which includes a cooling channel 110 and a storage container 120.

[0036] S100: Obtain information on natural disasters.

[0037] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in nuclear power plants includes obtaining information on natural disasters. It is understood that the types of natural disasters in this embodiment mainly include typhoons, floods, and earthquakes.

[0038] Specifically, the emergency assessment method for dry-storage spent fuel in nuclear power plants can be connected to the nuclear power plant's main control system to obtain relevant natural disaster information. Understandably, the main control system of a nuclear power plant typically integrates various monitoring devices and sensors to monitor environmental parameters in real time, including meteorological conditions and seismic information. This data can be provided to the emergency assessment method to enable a rapid response in the event of a natural disaster.

[0039] Specifically, it is also possible to obtain early warning information for regularly occurring meteorological disasters, such as typhoons, by connecting to the websites of meteorological bureaus and local governments. It is also possible to obtain information on seismic activity, including the time, location, and magnitude of earthquakes, by connecting to the website interfaces of earthquake monitoring agencies. Furthermore, it is possible to obtain information such as flood levels through hydrological departments.

[0040] Understandably, the purpose of obtaining information on natural disasters is to enable timely early warning, monitoring, and assessment of potential disaster risks, thereby taking appropriate measures to ensure the safe operation of nuclear power plants.

[0041] S200: Obtain the type and risk parameters of natural disasters based on natural disaster information.

[0042] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in nuclear power plants obtains the type and risk parameters of natural disasters based on natural disaster information.

[0043] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in nuclear power plants analyzes the collected natural disaster information through specific algorithms and models to identify the specific type of disaster, such as typhoon, flood or earthquake.

[0044] In this embodiment of the application, once the disaster type is determined, the emergency assessment method for dry storage of spent fuel in nuclear power plants will continue to conduct risk assessments to obtain risk parameters. It is understood that risk parameters include information such as typhoon level, flood intensity, and earthquake intensity.

[0045] In this embodiment, environmental impact parameters are obtained based on the type of natural disaster and risk parameters. It is understood that when the type of natural disaster is a typhoon, the environmental impact parameter is wind speed. It is understood that when the type of natural disaster is a flood, the environmental impact parameters are static water pressure and water flow velocity. It is understood that when the type of natural disaster is an earthquake, the environmental impact parameters are horizontal acceleration and vertical acceleration.

[0046] Specifically, for typhoons, weather stations or other meteorological monitoring equipment can be used to monitor wind speed in real time. For floods, hydrological stations, water level gauges, and other equipment can be used to monitor water levels and flow velocity. For earthquakes, seismic monitoring instruments and accelerometers are used to monitor the horizontal and vertical acceleration of the earthquake. Understandably, in the actual operation of nuclear power plants, specialized monitoring equipment and sensors are typically deployed to ensure timely acquisition of environmental impact parameters during natural disasters. Furthermore, nuclear power plants also establish corresponding monitoring systems to monitor and record these parameters in real time, in preparation for emergency response.

[0047] S300: In response to a risk parameter exceeding the response threshold, obtain the radiation dose of the concrete module.

[0048] In this embodiment, the emergency assessment method for dry-storage spent fuel in nuclear power plants obtains the radiation dose of the concrete module 100 in response to risk parameters exceeding a response threshold. It is understood that the response threshold is 477 km / h when the natural disaster type is a typhoon. When the natural disaster type is a flood, the response threshold is 15.24 m (50 ft) of static water pressure and 4.572 m / s (15 ft / s) of water flow velocity.

[0049] It is understood that the dry nuclear horizontal modular storage system 10 provided in this application embodiment was designed with the effects of typhoons (hurricanes) and their loads in mind. The design is based on the most severe typhoon (hurricane) loads specified in NUREG-0800-(8.19) and (8.30). Furthermore, the effects of typhoon-generated projectiles are considered to ensure the system can withstand this additional challenge. It is understood that NUREG-0800-(8.19) and (8.30) are part of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, which primarily covers guidance on typhoon and hurricane load analysis for pressurized water reactor (LWR) nuclear power plants.

[0050] It is understood that the dry nuclear horizontal modular storage system 10 provided in this application embodiment also takes into account the possible impact of tsunamis, floods and earthquakes on the dry nuclear horizontal modular storage system 10 during its design.

[0051] In this embodiment, a neutron dose equivalent rate meter or a gamma dose rate monitor may be installed at the concrete module 100. The neutron dose equivalent rate meter or gamma dose rate monitor can be used to monitor the radiation dose of the dry nuclear-level modular storage system 10. It is understood that these monitoring instruments can measure the radiation levels of neutrons or gamma rays in the surrounding environment, thereby obtaining radiation dose data. This data can be transmitted to the system's control center for analysis and evaluation by operators.

[0052] It is understood that the radiation dose in the embodiments of this application can be measured in terms of dose rate. Dose rate represents the radiation energy per unit area or unit volume per unit time, typically measured in units of hour or second. Specifically, dose rate includes neutron dose rate and gamma-ray dose rate. Neutron dose rate measures the energy transfer rate of neutron radiation, typically measured in units of area or volume per unit time, and gamma-ray dose rate measures the energy transfer rate of gamma-ray radiation. Gamma-ray dose rate measures the energy transfer rate of gamma-ray radiation, typically measured in units of area or volume per unit time, and gamma-ray dose rate measures the energy transfer rate of gamma-ray radiation, typically measured in units of area or volume per unit time.

[0053] Understandably, by installing a neutron dose equivalent rate meter or a gamma dose rate monitor at the concrete module 100, real-time monitoring of the radiation dose of the dry nuclear-level modular storage system 10 can be achieved. This provides crucial data support for subsequent steps in the emergency assessment methodology, ensuring the system can respond promptly in abnormal situations.

[0054] In other embodiments, once a neutron dose equivalent rate meter or gamma dose rate monitor at the concrete module 100 detects a radiation dose exceeding a preset radiation dose threshold, the emergency assessment method for dry-stored spent fuel in a nuclear power plant enters the response phase. In this phase, the emergency assessment method automatically identifies and confirms an abnormal state of the dry-level modular nuclear storage system 10. This abnormal state may indicate that the system is experiencing abnormal radiation levels, which could be due to problems such as blocked cooling channels or component damage.

[0055] Understandably, emergency assessment methods for dry-storage spent fuel at nuclear power plants determine the severity of anomalies based on pre-defined standards and strategies, and decide on appropriate emergency response measures. These measures may include immediately shutting down system operations, activating backup cooling mechanisms, and notifying operators. By responding quickly to abnormal radiation doses, the system can minimize the impact of anomalies on the system and the environment, thereby ensuring stable system operation.

[0056] Understandably, the emergency assessment method for dry-storage spent fuel in nuclear power plants can record and store relevant information about abnormal states, including the time, location, and radiation dose level of the anomaly. This information is crucial for subsequent emergency management and analysis. By accurately identifying abnormal states, the system can provide a precise basis for subsequent emergency management plans and measures, thereby effectively addressing potential risks and problems.

[0057] Specifically, in the embodiments of this application, the radiation dose threshold is a neutron dose rate or gamma-ray dose rate greater than or equal to 250 millirems per hour (mRem / hr).

[0058] S400: Obtain the effective multiplication coefficient of the storage container based on the radiation dose.

[0059] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in nuclear power plants also includes obtaining the effective multiplication factor of the storage container 120 based on the radiation dose.

[0060] Specifically, the nuclear reaction process within the storage container 120 can be obtained by inputting the radiation dose acquired at various points into a pre-set radiation field model of the storage container. The effective multiplication coefficient of the storage container 120 can then be obtained through the nuclear reaction process within the storage container 120.

[0061] S500: In response to the effective proliferation coefficient being higher than the effective proliferation coefficient threshold, a storage container transfer operation is performed.

[0062] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in nuclear power plants also includes performing a transfer operation of storage container 120 in response to the effective multiplication coefficient being higher than the effective multiplication coefficient threshold.

[0063] In this embodiment of the application, during spent fuel storage, the emergency assessment method for dry-stored spent fuel in nuclear power plants continuously predicts the storage status of the spent fuel, including the effective multiplication factor (K). eff The effective proliferation coefficient threshold is 0.95.

[0064] It is understandable that when K effWhen the value exceeds 0.95, the emergency assessment method for dry storage of spent fuel at nuclear power plants will be used to relocate storage container 120 in accordance with the response procedures. This includes moving spent fuel storage container 120 from its current location to a safer location to ensure the safe storage of spent fuel.

[0065] Specifically, the spent fuel assemblies inside storage container 120 can be cut up in preparation for subsequent disposal, ensuring that the spent fuel assemblies can be safely handled during the disposal process. It is understood that the safe disposal of the cut spent fuel assemblies is to ensure the safe operation of the nuclear facility, including moving the spent fuel assemblies to a specific disposal area to ensure that they do not pose a threat to the environment.

[0066] Understandably, the effective proliferation coefficient (K) eff K is a parameter describing the fission chain reaction in nuclear reactions. It represents the average number of fission neutrons produced per fission neutron in a fission chain reaction under steady-state conditions; it can also be understood as the fission chain reaction multiplication factor. When K... eff When K is greater than 1, it indicates that the nuclear reaction is in a supercritical state, and each fission neutron in the fission chain reaction produces, on average, more than one new fission neutron, and the reaction will continue to grow. eff When K equals 1, it indicates that the nuclear reaction is in a critical state, where each fission neutron in the fission chain reaction produces an average of one new fission neutron, and the reaction is self-sustaining. eff A value less than 1 indicates that the nuclear reaction is in a subcritical state, where each fission neutron in the fission chain reaction produces, on average, less than one new fission neutron, and the reaction gradually weakens. In the field of spent fuel storage, to ensure the safety of nuclear facilities, maintaining K0... eff It is essential below 0.95.

[0067] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in a nuclear power plant further includes obtaining the degree of damage to the concrete module 100. Then, based on the degree of damage, information on damaged components is obtained, and based on this information, a repair sequence for the damaged components is determined. Finally, the damaged components are repaired according to the repair sequence.

[0068] Specifically, the extent of damage to the concrete module 100 can be assessed through visual inspection, instrument measurement, or other appropriate methods to determine the potential damage, including but not limited to cracks, breaks, and displacement. Subsequently, based on the damage assessment, the specific components affected are identified, and information such as the type, location, and extent of damage is recorded. Next, a repair priority is established based on the information about the damaged components. Typically, components that have the greatest impact on the safety of the concrete module 100 are addressed first. Finally, the damaged components are repaired or replaced accordingly. Repair methods may include filling, curing, reinforcement, or replacement.

[0069] Understandably, the emergency assessment method for dry storage of spent fuel in nuclear power plants can ensure that damaged components are repaired in a timely manner after a natural disaster, thereby ensuring the integrity and safety of the nuclear power plant system.

[0070] Figure 4 This is a schematic diagram illustrating the implementation process of an emergency assessment method for dry storage of spent fuel in nuclear power plants, provided in another embodiment of this application. Figure 4 As shown, the emergency assessment method for dry storage of spent fuel in nuclear power plants includes at least the following steps: S510: obtaining radiation dose and a radiation field model of the storage container; S520: simulating the nuclear reaction process inside the storage container based on the radiation field model of the storage container; S530: obtaining the neutron production rate and neutron loss rate based on the nuclear reaction process; S540: obtaining the effective multiplication coefficient based on the neutron production rate and neutron loss rate.

[0071] S510: Obtain radiation dose and radiation field model of storage container.

[0072] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in nuclear power plants also includes obtaining the radiation dose and the radiation field model of the storage container 120.

[0073] It is understood that the dry nuclear-level modular storage system 10 includes a neutron dose equivalent rate meter or a gamma dose rate monitor. The radiation dose of the dry nuclear-level modular storage system 10 can be monitored through the neutron dose equivalent rate meter or the gamma dose rate monitor.

[0074] Understandably, multiple monitoring devices can be installed at different locations within the dry nuclear horizontal modular storage system 10 to obtain the radiation dose of the dry nuclear horizontal modular storage system 10. Specifically, the monitoring device locations can be set at 100 meters from the storage area of ​​the dry nuclear horizontal modular storage system 10, at the bird netting at the front of the concrete module 100, at the center line of the door opening cover of the concrete module 100, and at the rear shielding wall of the concrete module 100.

[0075] S520: Simulate the nuclear reaction process inside the storage container based on the radiation field model of the storage container.

[0076] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in nuclear power plants also includes simulating the nuclear reaction process inside the storage container based on a radiation field model of the storage container.

[0077] It is understandable that the radiation field model of the storage container can be a pre-set radiation field model of the storage container. By inputting the radiation dose obtained at each point into the model, the nuclear reaction process inside the storage container 120 can be obtained.

[0078] S530: Obtain the neutron production rate and neutron loss rate based on the nuclear reaction process.

[0079] In this embodiment of the application, the emergency assessment method for dry storage of spent fuel in nuclear power plants also includes obtaining the neutron production rate and neutron loss rate based on the nuclear reaction process.

[0080] Specifically, the neutron production rate and neutron loss rate during the nuclear reaction process can be obtained from the nuclear reaction process within the storage container 120.

[0081] S540: Obtain the effective multiplication coefficient based on the neutron production rate and neutron loss rate.

[0082] It is understood that the emergency assessment method for dry storage of spent fuel in nuclear power plants provided in this application embodiment can obtain an effective multiplication coefficient based on the neutron generation rate and the neutron loss rate.

[0083] Specifically, the effective proliferation coefficient (K) eff The estimation method for ) can be obtained by formula (1).

[0084]

[0085] It is understood that the emergency assessment method for dry storage of spent fuel in nuclear power plants provided in this application can provide a reliable means of assessing the storage system, enabling it to maintain safe and stable operation under various working conditions.

[0086] Figure 5 This is a schematic diagram of an emergency assessment system 20 for dry storage of spent fuel in a nuclear power plant, provided in one embodiment of this application. Figure 5 As shown, the nuclear power plant dry storage spent fuel emergency assessment system 20 includes at least the following components: disaster information acquisition module 21, risk assessment module 22, radiation dose acquisition module 23, effective multiplication coefficient acquisition module 24, and execution module 25.

[0087] It is understood that the nuclear power plant dry storage spent fuel emergency assessment system 20 provided in this application embodiment is applied to, for example, Figures 3 to 4 The method for emergency assessment of dry storage of spent fuel in nuclear power plants is shown.

[0088] In this embodiment, the disaster information acquisition module 21 is used to acquire information about natural disasters; please refer to the specific acquisition method for details. Figures 1 to 4 The details and their corresponding descriptions will not be repeated here.

[0089] In this embodiment, the risk assessment module 22 is used to obtain the type and risk parameters of natural disasters based on natural disaster information. Please refer to the documentation for the specific determination method. Figures 1 to 4 The details and their corresponding descriptions will not be repeated here.

[0090] In this embodiment, the radiation dose acquisition module 23 acquires the radiation dose of the concrete module 100 in response to a risk parameter exceeding a response threshold. Please refer to the documentation for the specific generation method. Figures 1 to 4 The details and their corresponding descriptions will not be repeated here.

[0091] In this embodiment, the emergency management plan execution module 24 is used to obtain the effective multiplication coefficient of the storage container 120 based on the radiation dose. Please refer to the following for details on the execution and acquisition methods. Figures 1 to 4 The details and their corresponding descriptions will not be repeated here.

[0092] In this embodiment, the execution module 25 performs a transfer operation on the storage container 120 in response to the effective proliferation coefficient being higher than the effective proliferation coefficient threshold. Please refer to the following for details on the execution and acquisition methods. Figures 1 to 4 The details and their corresponding descriptions will not be repeated here.

[0093] It should be understood that the sequence number of each step in the above embodiments does not imply the order of execution. The execution order of each process should be determined by its function and internal logic, and should not constitute any limitation on the implementation process of the embodiments of this application.

[0094] Figure 6 This is a schematic diagram of a terminal device 6 provided in an embodiment of this application. For example... Figure 6 As shown, the terminal device 6 in this embodiment includes: a processor 60, a memory 61, and a computer program 62, such as a software program, stored in the memory 61 and executable on the processor 60. When the processor 60 executes the computer program 62, it implements the steps in the above embodiments of the emergency assessment methods for dry storage of spent fuel in nuclear power plants. Alternatively, when the processor 60 executes the computer program 62, it implements the functions of each module / unit in the above embodiments of the apparatus.

[0095] For example, the computer program 62 can be divided into one or more modules / units, which are stored in the memory 61 and executed by the processor 60 to complete this application. The one or more modules / units can be a series of computer program instruction segments capable of performing specific functions, which describe the execution process of the computer program 62 in the terminal device 6. For example, the computer program 62 can be divided into: software functional units.

[0096] The terminal device 6 can be a desktop computer, laptop, handheld computer, or cloud server, etc. The terminal device 6 may include, but is not limited to, a processor 60 and a memory 61. Those skilled in the art will understand that... Figure 6 This is merely an example of terminal device 6 and does not constitute a limitation on terminal device 6. It may include more or fewer components than shown, or combine certain components, or different components. For example, terminal device 6 may also include input / output devices, network access devices, buses, etc.

[0097] The processor 60 may be a Central Processing Unit (CPU), or other general-purpose processors, digital signal processors (DSPs), application-specific integrated circuits (ASICs), field-programmable gate arrays (FPGAs), or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. A general-purpose processor may be a microprocessor or any conventional processor.

[0098] The memory 61 can be an internal storage unit of the terminal device 6, such as a hard disk or memory of the terminal device 6. The memory 61 can also be an external storage device of the terminal device 6, such as a plug-in hard disk, Smart Media Card (SMC), Secure Digital (SD) card, or Flash Card equipped on the terminal device 6. Furthermore, the memory 61 can include both internal and external storage units of the terminal device 6. The memory 61 is used to store the computer program and other programs and data required by the terminal device 6. The memory 61 can also be used to temporarily store data that has been output or will be output.

[0099] Those skilled in the art will clearly understand that, for the sake of convenience and brevity, the above-described division of functional units and modules is merely an example. In practical applications, the above functions can be assigned to different functional units and modules as needed, that is, the internal structure of the device can be divided into different functional units or modules to complete all or part of the functions described above. The functional units and modules in the embodiments can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or as a software functional unit. Furthermore, the specific names of the functional units and modules are only for easy differentiation and are not intended to limit the scope of protection of this application. The specific working process of the units and modules in the above system can be referred to the corresponding process in the foregoing method embodiments, and will not be repeated here.

[0100] In the above embodiments, the descriptions of each embodiment have different focuses. For parts that are not described in detail or recorded in a certain embodiment, please refer to the relevant descriptions of other embodiments.

[0101] Those skilled in the art will recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementation should not be considered beyond the scope of this application.

[0102] In the embodiments provided in this application, it should be understood that the disclosed devices / terminal equipment and methods can be implemented in other ways. For example, the device / terminal equipment embodiments described above are merely illustrative. For instance, the division of modules or units is only a logical functional division, and in actual implementation, there may be other division methods. For example, multiple units or components may be combined or integrated into another system, or some features may be ignored or not executed. Furthermore, the displayed or discussed mutual coupling or direct coupling or communication connection may be through some interfaces; the indirect coupling or communication connection between devices or units may be electrical, mechanical, or other forms.

[0103] The units described as separate components may or may not be physically separate. The components shown as units may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the units can be selected to achieve the purpose of this embodiment according to actual needs.

[0104] Furthermore, the functional units in the various embodiments of this application can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or as a software functional unit.

[0105] If the integrated module / unit is implemented as a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, all or part of the processes in the methods of the above embodiments can also be implemented by hardware related to computer program instructions. The computer program can be stored in a computer-readable storage medium, and when executed by a processor, it can implement the steps of the various method embodiments described above. The computer program includes computer program code, which can be in the form of source code, object code, executable files, or certain intermediate forms. The computer-readable medium can include: any entity or device capable of carrying the computer program code, recording media, USB flash drives, portable hard drives, magnetic disks, optical disks, computer memory, read-only memory (ROM), random access memory (RAM), electrical carrier signals, telecommunication signals, and software distribution media, etc. It should be noted that the content included in the computer-readable medium can be appropriately added or removed according to the requirements of legislation and patent practice in the jurisdiction. For example, in some jurisdictions, according to legislation and patent practice, computer-readable media do not include electrical carrier signals and telecommunication signals.

[0106] The above-described embodiments are only used to illustrate the technical solutions of this application, and are not intended to limit them. Although this application has been described in detail with reference to the foregoing embodiments, those skilled in the art should understand that modifications can still be made to the technical solutions described in the foregoing embodiments, or equivalent substitutions can be made to some of the technical features. Such modifications or substitutions do not cause the essence of the corresponding technical solutions to deviate from the spirit and scope of the technical solutions of the embodiments of this application, and should all be included within the protection scope of this application.

Claims

1. A method for emergency assessment of dry-type spent fuel storage in nuclear power plants, applied to a dry-type modular nuclear horizontal storage system, wherein the dry-type modular nuclear horizontal storage system includes concrete modules and storage containers, characterized in that... The method includes: Obtain information about natural disasters; Based on the natural disaster information, obtain the type and risk parameters of the natural disaster; In response to the risk parameter being higher than a response threshold, the radiation dose of the concrete module is obtained; The effective multiplication coefficient of the storage container is obtained based on the radiation dose. In response to the effective proliferation coefficient being higher than the effective proliferation coefficient threshold, the storage container transfer operation is performed; The step of obtaining the effective multiplication coefficient of the storage container based on the radiation dose includes: Obtain the radiation dose and the radiation field model of the storage container; The nuclear reaction process inside the storage container was simulated based on the radiation field model of the storage container; The neutron production rate and neutron loss rate are obtained based on the described nuclear reaction process; The effective multiplication coefficient is obtained based on the neutron production rate and the neutron loss rate. After obtaining the radiation dose of the concrete module, the method further includes: Obtain the degree of damage to the concrete module; Information on damaged components is obtained based on the degree of damage. The repair sequence of the damaged components is obtained based on the information of the damaged components; Repair the damaged components according to the repair sequence described above; The repairability of the damaged component is determined based on the degree of damage. In response to the repairability of the damaged component being below a repairability threshold, the storage container transfer operation is performed.

2. The emergency assessment method for dry storage of spent fuel in nuclear power plants according to claim 1, characterized in that, The types of natural disasters mentioned include typhoons, floods, and earthquakes.

3. The emergency assessment method for dry storage of spent fuel in nuclear power plants according to claim 1, characterized in that, The method further includes: Environmental impact parameters are obtained based on the type of natural disaster and the risk parameters. When the type of natural disaster is a typhoon, the environmental impact parameter is wind speed; When the type of natural disaster is flood, the environmental impact parameters are static water pressure and water flow velocity; When the type of natural disaster is an earthquake, the environmental impact parameters are horizontal acceleration and vertical acceleration.

4. The emergency assessment method for dry storage of spent fuel in nuclear power plants according to claim 1, characterized in that, When the type of natural disaster is a typhoon, the response threshold is 477 kilometers per hour.

5. The emergency assessment method for dry storage of spent fuel in nuclear power plants according to claim 1, characterized in that, When the type of natural disaster is flood, the response threshold is 15.24 meters of static water pressure and 4.572 meters per second of water flow velocity.

6. The emergency assessment method for dry storage of spent fuel in nuclear power plants according to claim 1, characterized in that, When the type of natural disaster is an earthquake, the response threshold is 0.3g horizontal acceleration and 0.25g vertical acceleration.

7. The emergency assessment method for dry storage of spent fuel in nuclear power plants according to claim 1, characterized in that, The effective proliferation coefficient threshold is 0.

95.

8. An emergency assessment system for dry-storage spent fuel in nuclear power plants, applied to the steps of the method as described in any one of claims 1 to 7, characterized in that, The system includes: A disaster information acquisition module, wherein the disaster information acquisition module is used to acquire information about natural disasters; The risk assessment module is used to obtain the type and risk parameters of the natural disaster based on the natural disaster information. A radiation dose acquisition module, wherein the radiation dose acquisition module acquires the radiation dose of the concrete module in response to the risk parameter being higher than a response threshold; An effective multiplication coefficient acquisition module is used to acquire the effective multiplication coefficient of the storage container based on the radiation dose. The execution module, in response to the effective multiplication coefficient being higher than the effective multiplication coefficient threshold, performs the storage container transfer operation; The step of obtaining the effective multiplication coefficient of the storage container based on the radiation dose includes: Obtain the radiation dose and the radiation field model of the storage container; The nuclear reaction process inside the storage container was simulated based on the radiation field model of the storage container; The neutron production rate and neutron loss rate are obtained based on the described nuclear reaction process; The effective multiplication coefficient is obtained based on the neutron production rate and the neutron loss rate. After obtaining the radiation dose of the concrete module, the method further includes: Obtain the degree of damage to the concrete module; Information on damaged components is obtained based on the degree of damage. The repair sequence of the damaged components is obtained based on the information of the damaged components; Repair the damaged components according to the repair sequence described above; The repairability of the damaged component is determined based on the degree of damage. In response to the repairability of the damaged component being below a repairability threshold, the storage container transfer operation is performed.

9. A terminal device, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that, When the processor executes the computer program, it implements the steps of the method as described in any one of claims 1 to 7.

10. A computer-readable storage medium storing a computer program, characterized in that, When the computer program is executed by a processor, it implements the steps of the method as described in any one of claims 1 to 7.

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