CN117391432A - Nuclear power station dry-type stored spent fuel emergency assessment method, system, equipment and medium - Google Patents
Nuclear power station dry-type stored spent fuel emergency assessment method, system, equipment and medium Download PDFInfo
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Abstract
The application provides a nuclear power station dry-type stored spent fuel emergency assessment method, a system, equipment and a medium, which are applied to a dry-type nuclear horizontal modularized storage system, wherein the dry-type nuclear horizontal modularized storage system comprises a concrete module and a storage container, and the method comprises the following steps: acquiring information of natural disasters; acquiring the type and risk parameters of the natural disasters according to the natural disaster information; acquiring a radiation dose of the concrete module in response to the risk parameter being above a response threshold; obtaining an effective proliferation factor of the storage vessel based on the radiation dose; and in response to the effective proliferation coefficient being higher than an effective proliferation coefficient threshold, performing the storage container transfer operation, and integrating natural disaster risk assessment, radiation dose monitoring and effective proliferation coefficient control together to form a complete emergency assessment and response system, so that the overall efficiency of the nuclear power station in coping with disasters is improved.
Description
Technical Field
The application belongs to the field of spent fuel management, and particularly relates to a dry-type stored spent fuel emergency assessment method, system, equipment and medium for a nuclear power station.
Background
Dry storage of spent fuel is a technology used in the nuclear energy field for long-term storage of spent nuclear fuel. Dry storage does not require a large amount of water resources and can more effectively control the release of radioactive materials than conventional wet storage (storage of nuclear fuel in a pool), thereby reducing environmental and health risks.
Currently, the dry nuclear horizontal modular storage (Nuclear Horizontal Modular Storage, NUHOMS) system is a heat sink system that transfers decay heat of spent fuel to the storage vessel (Dry Storage Canister, DSC) by conduction, radiation, and natural convection, and then transfers heat from the double welded sealed storage vessel to the surrounding air through cooling channels in the concrete module (Horizontal Storage Module-Hot, HSM-H). Methods for assessing the availability of dry core horizontal modular storage systems in extreme weather are lacking in the related art.
Disclosure of Invention
In view of this, embodiments of the present application provide methods, systems, devices and media for emergency assessment of dry stored spent fuel in nuclear power plants to address the lack of methods in the prior art for assessing availability of dry nuclear horizontal modular storage systems in extreme weather conditions.
A first aspect of an embodiment of the present application provides a method for emergency assessment of dry stored spent fuel in a nuclear power plant, applied to a dry-type nuclear horizontal modular storage system, the dry-type nuclear horizontal modular storage system including a concrete module and a storage container, the method comprising: acquiring information of natural disasters; acquiring the type and risk parameters of the natural disasters according to the natural disaster information; acquiring a radiation dose of the concrete module in response to the risk parameter being above a response threshold; obtaining an effective proliferation factor of the storage vessel based on the radiation dose; the storage vessel transfer operation is performed in response to the effective proliferation coefficient being above an effective proliferation coefficient threshold.
With reference to the first aspect, in a first possible implementation manner of the first aspect, the obtaining an effective proliferation coefficient of the storage container according to the radiation dose includes: acquiring a radiation field model of the radiation dose and the storage container; simulating a nuclear reaction process within the storage vessel according to a radiation field model of the storage vessel; obtaining neutron production rate and neutron loss rate according to the nuclear reaction process; and obtaining the effective proliferation coefficient according to the neutron production rate and the neutron loss rate.
With reference to the first aspect, in a second possible implementation manner of the first aspect, after the acquiring a radiation dose of the concrete module, the method further includes: obtaining the damage degree of the concrete module; obtaining damaged part information according to the damage degree; obtaining damaged part repair sequences according to the damaged part information; and repairing the damaged part according to the damaged part repairing sequence.
With reference to the first aspect, in a third possible implementation manner of the first aspect, the method further includes: obtaining repairability of the damaged part according to the damage degree; the storage container transfer operation is performed in response to the repairability of the damaged component being below a repairability threshold.
With reference to the first aspect, in a fourth possible implementation manner of the first aspect, the type of the natural disaster includes typhoons, floods, and earthquakes.
With reference to the first aspect, in a fifth possible implementation manner of the first aspect, the method further includes: acquiring environmental influence parameters according to the type of the natural disasters and the risk parameters; when the natural disaster is typhoon, the environment influence parameter is wind speed; when the natural disasters are of the type of flood, the environmental influence parameters are static water pressure and water flow speed; when the natural disasters are earthquake, the environment influence parameters are horizontal acceleration and vertical acceleration.
With reference to the first aspect, in a sixth possible implementation manner of the first aspect, when the type of the natural disaster is typhoon, the response threshold is 477 km/h.
With reference to the first aspect, in a seventh possible implementation manner of the first aspect, when the natural disaster is of a flood type, the response threshold is 15.24 meters of static water pressure and 4.572 meters per second of water flow speed.
With reference to the first aspect, in an eighth possible implementation manner of the first aspect, when the type of the natural disaster is an earthquake, the response threshold is 0.3g of horizontal acceleration and 0.25g of vertical acceleration.
With reference to the first aspect, in a ninth possible implementation manner of the first aspect, the effective proliferation factor threshold is 0.95.
A second aspect of embodiments of the present application provides a dry stored spent fuel emergency assessment system for a nuclear power plant, for use in the steps of the method according to the first aspect, the system comprising: the disaster information acquisition module is used for acquiring information of natural disasters; the risk assessment module is used for acquiring the type and risk parameters of the natural disasters according to the natural disaster information; a radiation dose acquisition module that acquires a radiation dose of the concrete module in response to the risk parameter being above a response threshold; an effective proliferation factor obtaining module for obtaining an effective proliferation factor of the storage container according to the radiation dose; an execution module that performs the storage container transfer operation in response to the effective proliferation coefficient being above an effective proliferation coefficient threshold.
A third aspect of the embodiments of the present application provides a terminal device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, the processor implementing the steps of the method according to any one of the first aspects when the computer program is executed.
A fourth aspect of the embodiments of the present application provides a computer-readable storage medium storing a computer program which, when executed by a processor, implements the steps of the method according to any one of the first aspects.
Compared with the prior art, the embodiment of the application has the beneficial effects that: by integrating natural disaster risk assessment, radiation dose monitoring and effective proliferation coefficient control, a complete emergency assessment and response system is formed, and the overall efficiency of the nuclear power station for coping with disasters is improved.
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In order to more clearly illustrate the technical solutions of the embodiments of the present application, the drawings that are required for the embodiments or the description of the prior art will be briefly described below, it being obvious that the drawings in the following description are only some embodiments of the present application, and that other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic illustration of a dry core horizontal modular storage system provided in an embodiment of the present application;
FIG. 2 is a schematic view of a concrete module provided in an embodiment of the present application;
fig. 3 is a schematic implementation flow chart of a method for emergency assessment of dry stored spent fuel in a nuclear power plant according to an embodiment of the present application;
fig. 4 is a schematic implementation flow chart of a method for emergency assessment of dry stored spent fuel in a nuclear power plant according to an embodiment of the present application;
FIG. 5 is a schematic diagram of a nuclear power plant dry stored spent fuel emergency assessment system provided by an embodiment of the present application;
fig. 6 is a schematic diagram of a terminal device provided in an embodiment of the present application.
Detailed Description
In the following description, for purposes of explanation and not limitation, specific details are set forth, such as particular system configurations, techniques, etc. in order to provide a thorough understanding of the embodiments of the present application. It will be apparent, however, to one skilled in the art that the present application may be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present application with unnecessary detail.
Currently, the dry nuclear horizontal modular storage (Nuclear Horizontal Modular Storage, NUHOMS) system is a heat sink system that transfers decay heat of spent fuel to the storage vessel (Dry Storage Canister, DSC) by conduction, radiation, and natural convection, and then transfers heat from the double welded sealed storage vessel to the surrounding air through cooling channels in the concrete module (Horizontal Storage Module-Hot, HSM-H). Methods of evaluating dry core horizontal modular storage system availability in extreme weather conditions are described in the related art. Especially under the influence of extreme weather such as typhoons, earthquakes, floods, etc., the concrete module may be displaced or deformed, and the storage container may be deformed. Furthermore, extreme weather may also affect the shielding function of the dry core horizontal modular storage system, thereby resulting in an increased radiation dose of the system.
The emergency assessment method, system, equipment and medium for the dry stored spent fuel of the nuclear power station have remarkable beneficial effects in the field of dry-type horizontal modularized storage systems. By integrating natural disaster risk assessment, radiation dose monitoring and effective proliferation coefficient control, a complete emergency assessment and response system is formed, and the overall efficiency of the nuclear power station for coping with disasters is improved.
In order to illustrate the technical solutions described in the present application, the following description is made by specific examples.
Fig. 1 is a schematic diagram of a dry core horizontal modular storage system 10 provided in an embodiment of the present application, as shown in fig. 1, the dry core 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 will be appreciated that the distribution and arrangement of the concrete modules in the system is based on safety and storage efficiency considerations to ensure that the system will operate stably under different conditions.
Referring to fig. 2 together, fig. 2 is a schematic view of a concrete module 100 according to an embodiment of the disclosure. As shown in fig. 2, the concrete module 100 includes at least a cooling flow passage 110 and a storage container 120.
It will be appreciated that the number of concrete modules included in the dry core horizontal modular storage system 10 of the present embodiments is merely one example, and that one skilled in the art may design a greater or lesser number of concrete modules depending on the actual situation, and the present application is not limited in this regard.
It will be appreciated that the cooling runner 110 is designed to transfer decay heat of the spent fuel away by natural convection, radiation, etc., to maintain a stable temperature of the dry nuclear horizontal modular storage system 10. The storage container 120 carries spent fuel to ensure its safe storage. The proper design of the layout and structure of these core elements is that the entire dry core horizontal modular storage system 10 is capable of efficient heat dissipation.
Fig. 3 is a schematic implementation flow chart of a method for emergency assessment of dry stored spent fuel in a nuclear power station according to an embodiment of the present application. As shown in fig. 3, the emergency assessment method for dry-stored spent fuel in the nuclear power plant at least comprises the following steps: s100: acquiring information of natural disasters; s200: acquiring the type and risk parameters of the natural disasters according to the natural disaster information; s300: acquiring the radiation dose of the concrete module in response to the risk parameter being above the response threshold; s400: obtaining an effective proliferation coefficient of the storage container according to the radiation dose; s500: in response to the effective proliferation coefficient being above the effective proliferation coefficient threshold, performing a storage container transfer operation.
The emergency assessment method for dry-type stored spent fuel in a nuclear power plant is applied to a dry-type horizontal modular storage system 10 shown in fig. 1 and a concrete module 100 shown in fig. 2, wherein the dry-type horizontal modular storage system 10 comprises the concrete module 100, and the concrete module 100 comprises a cooling runner 110 and a storage container 120.
S100: and acquiring information of the natural disasters.
In the embodiment of the application, the emergency assessment method for the dry-stored spent fuel in the nuclear power station comprises the steps of acquiring information of natural disasters. It is understood that the types of natural disasters in the embodiments of the present application mainly include typhoons, floods, and earthquakes.
Specifically, the emergency assessment method for the dry-type stored spent fuel of the nuclear power plant can obtain corresponding natural disaster information through a main control system connected to the nuclear power plant. It will be appreciated that the primary control system of a nuclear power plant typically integrates various monitoring devices and sensors for monitoring environmental parameters, including weather conditions, seismic information, etc., in real time. These data can be provided to an emergency assessment method to react quickly when a natural disaster occurs.
Specifically, the early warning information of a periodic weather disaster, such as typhoons, can be obtained by connecting the weather bureau and the local government website. Information about the seismic activity, including time of occurrence, location, magnitude, etc., may also be obtained through a website interface connected to the seismic monitoring mechanism. Information such as the water level of the flood can also be obtained by the hydrology department.
It can be appreciated that the purpose of acquiring natural disaster information is to be able to early warn, monitor and evaluate potential disaster risks in time, so that corresponding measures are taken to ensure safe operation of the nuclear power plant.
S200: and acquiring the type and risk parameters of the natural disasters according to the natural disaster information.
In the embodiment of the application, the nuclear power station dry-type stored spent fuel emergency assessment method obtains the type and risk parameters of the natural disasters according to the natural disaster information.
In the embodiment of the application, the nuclear power station dry-stored spent fuel emergency assessment method analyzes the collected natural disaster information through a specific algorithm and model to identify the specific type of the disaster, such as typhoons, floods or earthquakes.
In the embodiment of the application, once the disaster type is determined, the nuclear power station dry-stored spent fuel emergency assessment method can continue to perform risk assessment to obtain risk parameters. It will be appreciated that the risk parameters include typhoons level, flood intensity, seismic intensity, etc.
In the embodiment of the application, the environmental impact parameters are obtained according to the type of the natural disaster and the risk parameters. It will be appreciated that when the type of natural disaster is typhoon, the environmental impact parameter is wind speed. It will be appreciated that when the type of natural disaster is a flood, the environmental impact parameters are static water pressure and water flow velocity. It will be appreciated that when the type of natural disaster is an earthquake, the environmental impact parameters are horizontal acceleration and vertical acceleration.
In particular, for typhoons, weather stations or other weather monitoring devices may be used to monitor wind speed in real-time. For floods, water level and water velocity can be monitored using hydronic stations, water level gauges, and the like. For earthquakes, devices such as earthquake monitoring instruments and accelerometers are used for monitoring the horizontal acceleration and the vertical acceleration of the earthquakes. It will be appreciated that in actual operation of a nuclear power plant, specialized monitoring equipment and sensors are typically deployed to ensure timely acquisition of environmental impact parameters when a natural disaster occurs. In addition, the nuclear power plant also establishes a corresponding monitoring system for monitoring and recording these parameters in real time for emergency response in case of emergency.
S300: in response to the risk parameter being above the response threshold, a radiation dose of the concrete module is acquired.
In an embodiment of the application, the nuclear power plant dry-stored spent fuel emergency assessment method obtains the radiation dose of the concrete module 100 in response to the risk parameter being above a response threshold. It will be appreciated that when the type of natural disaster is typhoon, the response threshold is 477 km/h. When the natural disaster is of the flood type, the response threshold is 15.24 meters (50 feet) of static water pressure and a water flow rate of 4.572 meters per second (15 feet per second).
It will be appreciated that embodiments of the present application provide a dry core horizontal modular storage system 10 that is designed to take into account the effects of typhoons (hurricanes) and their loads. The design basis used NUREG-0800- (8.19) and (8.30) the most severe typhoon (hurricane) load specified. In addition, the impact of the flying object created by typhoons is also considered to ensure that the system is able to withstand this additional challenge. It will be appreciated that NUREG-0800- (8.19) and (8.30) are part of the detail design criteria for nuclear power plants (Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition), and mainly cover guidance regarding typhoon and hurricane load analysis for pressurized water reactor nuclear power plants (LWR, light Water Reactor).
It will be appreciated that the dry core horizontal modular storage system 10 provided by embodiments of the present application also contemplates tsunamis, floods, and earthquakes in designing the dry core horizontal modular storage system 10.
In embodiments of the present application, a neutron dose equivalent rate meter or a gamma dose rate monitor may be provided at the concrete module 100. Radiation dose monitoring of the dry core level modular storage system 10 may be accomplished by neutron dose equivalent rate or gamma dose rate monitors. It will be appreciated that these monitoring instruments are capable of measuring the radiation level of neutrons or gamma rays in the surrounding environment to obtain radiation dose data. These data may be transmitted to a control center of the system for analysis and evaluation by an operator.
It will be appreciated that the radiation dose in embodiments of the present application may be measured in terms of dose rate. Dose rate refers to the radiant energy per unit area or unit volume per unit time, typically measured in units of hours or seconds. Specifically, the Dose Rate includes a neutron Dose Rate (Neutron Dose Rate) and a Gamma Dose Rate (Gamma Dose Rate). Where neutron dose rate is a measure of the rate of energy transfer of neutron radiation, typically in units of area per unit of time or units of gamma radiation. The gamma ray dose rate is expressed by expressing the energy of neutron radiation in a volume in terms of the energy of gamma ray radiation in a unit area or a unit volume in a unit time; gamma ray dose rate is a measure of the rate of energy transfer of gamma ray radiation, typically expressed in terms of energy per unit area or volume per unit time.
It will be appreciated that real-time monitoring of the radiation dose of the dry core horizontal modular storage system 10 may be achieved by providing a neutron dose equivalent rate meter or gamma dose rate monitor at the concrete module 100. The method provides key data support for the subsequent steps of the emergency assessment method, and ensures that the system can respond in time under abnormal conditions.
In other embodiments, the nuclear power plant dry stored spent fuel emergency assessment method enters the response phase once a neutron dose equivalent rate meter or gamma dose rate monitor at the concrete module 100 detects that the radiation dose is above a preset radiation dose threshold. At this stage, the nuclear power plant dry stored spent fuel emergency assessment method automatically identifies and confirms the abnormal status of the dry nuclear horizontal modular storage system 10. This abnormal condition may indicate that the system is experiencing an abnormal radiation level, which may be due to some problem, such as blockage of the cooling flow passages, component damage, etc.
It can be appreciated that the emergency assessment method for dry-stored spent fuel in the nuclear power plant can judge the severity of the abnormal state according to preset standards and strategies, and determine what emergency response measures to take. This may include immediately stopping the operation of the system, starting a backup cooling mechanism, notifying an operator, etc. By means of the rapid response to the radiation dose abnormality, the system can reduce the influence of the abnormal state on the system and the environment to the greatest extent, and therefore stable operation of the system is guaranteed.
It can be appreciated that the nuclear power plant dry-stored spent fuel emergency assessment method can record and store relevant information of abnormal states, including time, position, radiation dose level and the like of the occurrence of the abnormal states. This information is important for subsequent emergency management and analysis. By accurately determining the abnormal state, the system can provide accurate basis for subsequent emergency management schemes and measures, thereby effectively coping with potential risks and problems.
Specifically, in embodiments of the present application, the radiation dose threshold is a neutron dose rate or gamma ray dose rate of 250 millirem per hour (mRem/hr) or greater.
S400: the effective proliferation factor of the storage vessel is obtained from the radiation dose.
In an embodiment of the present application, the nuclear power plant dry-stored spent fuel emergency assessment method further includes obtaining an effective proliferation coefficient of the storage vessel 120 according to the radiation dose.
Specifically, the nuclear reaction process within the storage container 120 may be obtained by inputting the radiation doses acquired at the respective points into a preset storage container radiation field model. The effective proliferation factor of the storage vessel 120 is obtained through the nuclear reaction process in the storage vessel 120.
S500: in response to the effective proliferation coefficient being above the effective proliferation coefficient threshold, performing a storage container transfer operation.
In an embodiment of the present application, the nuclear power plant dry stored spent fuel emergency assessment method further includes performing a storage vessel 120 transfer operation in response to the effective proliferation factor being above an effective proliferation factor threshold.
In the embodiment of the application, during the spent fuel storage period, the dry stored spent fuel emergency assessment method of the nuclear power plant continuously predicts the storage state of the spent fuel, wherein the storage state comprises an effective proliferation coefficient (K eff ) Is a numerical value of (2). In the examples herein, the effective proliferation factor threshold is 0.95.
It will be appreciated that when K eff Beyond 0.95, the transfer operation of the storage vessel 120 will be performed in accordance with the responsive procedure nuclear power plant dry stored spent fuel emergency assessment method. This includes storing spent fuelThe container 120 is transferred from the current location to a safer location to ensure safe storage of the spent fuel.
In particular, the spent fuel assembly inside the storage vessel 120 may be ready for subsequent disposal by cutting to ensure that the spent fuel assembly can be safely handled during disposal. It will be appreciated that the spent fuel assembly being cut is safely disposed of to ensure safe operation of the nuclear power plant, including moving the spent fuel assembly to a specific disposal area to ensure it is not harmful to the environment.
It will be appreciated that the effective proliferation factor (K eff ) Refers to a parameter describing the fission chain reaction in the nuclear reaction. It represents the average number of production of each fission neutron in the fission chain reaction under steady state conditions, and can also be understood as the multiplication factor of the fission chain reaction. When K is eff Above 1, which means that the nuclear reaction is in a supercritical state, more than one new fission neutron is produced per fission neutron in the fission chain reaction on average, and the reaction is continuously increased. When K is eff Equal to 1 indicates that the nuclear reaction is in a critical state, and that each fissile neutron in the fission chain reaction produces on average a new fissile neutron, the reaction is self-sustaining. When K is eff Below 1, which indicates that the nuclear reaction is in a subcritical state, each fissile neutron in the fission chain reaction produces on average less than one new fissile neutron, and the reaction gradually weakens. In the field of spent fuel storage, K is maintained in order to ensure the safety of nuclear facilities eff Below 0.95 is indispensable.
In an embodiment of the present application, the method for emergency assessment of dry stored spent fuel in a nuclear power plant further includes obtaining a damage degree of the concrete module 100. And obtaining damaged part information according to the damage degree, obtaining damaged part repair sequence according to the damaged part information, and repairing the damaged part according to the damaged part repair sequence.
In particular, the extent of damage to the concrete module 100 may be inspected by visual inspection, instrumental measurement, or other corresponding method to determine the extent of damage that may be present, including but not limited to cracking, breakage, displacement, and the like. And then, determining which specific parts are affected according to the evaluation result of the damage degree, and recording information such as the type, the position, the degree and the like of the damaged parts. Next, a repair order is formulated based on the damaged component information. Typically, those components that have the greatest impact on the safety of the concrete module 100 will be preferentially treated. Finally, corresponding repair or replacement is performed for the damaged component. The method of repair may include filling, curing, reinforcing, replacement, etc.
It can be understood that the emergency assessment method for dry-type stored spent fuel in the nuclear power station can ensure that damaged parts are repaired in time after natural disasters occur so as to ensure the integrity and safety of a system of the nuclear power station.
Fig. 4 is a schematic implementation flow chart of a method for emergency assessment of dry stored spent fuel in a nuclear power plant according to another embodiment of the present application. As shown in fig. 4, the emergency assessment method for dry-stored spent fuel in the nuclear power plant at least comprises the following steps: s510: acquiring a radiation dose and a radiation field model of a storage container; s520: simulating a nuclear reaction process in the storage container according to the storage container radiation field model; s530: obtaining neutron production rate and neutron loss rate according to the nuclear reaction process; s540: and obtaining an effective proliferation coefficient according to the neutron production rate and the neutron loss rate.
S510: a radiation dose and a storage vessel radiation field model are acquired.
In an embodiment of the present application, the nuclear power plant dry stored spent fuel emergency assessment method further includes acquiring a radiation dose and a radiation field model (Radiation Dose and Radiation Field Model) of the storage vessel 120.
It will be appreciated that the modular storage system 10 includes a neutron dose equivalent rate meter or gamma dose rate monitor at the dry nuclear level. Radiation dose monitoring of the dry core level modular storage system 10 may be accomplished by neutron dose equivalent rate or gamma dose rate monitors.
It will be appreciated that a plurality of monitors may be provided at different locations of the dry core horizontal modular storage system 10 to obtain the radiation dose of the dry core horizontal modular storage system 10. In particular, monitor points may be located 100 meters from the storage area of the dry core horizontal modular storage system 10, at the bird net in front of the concrete module 100, at the door opening cover centerline of the concrete module 100, and at the rear shielding wall of the concrete module 100.
S520: the nuclear reaction process within the storage vessel is simulated according to the storage vessel radiation field model.
In an embodiment of the application, the emergency assessment method for dry-stored spent fuel in the nuclear power plant further comprises simulating a nuclear reaction process in the storage container according to the storage container radiation field model.
It will be appreciated that the reservoir radiation field model may be a pre-set reservoir radiation field model, and that nuclear reaction processes within the reservoir 120 may be obtained by inputting radiation doses acquired at various points into the model.
S530: the neutron production rate and neutron loss rate are obtained according to the nuclear reaction process.
In the embodiment of the application, the emergency assessment method for the dry-stored spent fuel of the nuclear power plant further comprises the step of acquiring a neutron production rate and a neutron loss rate according to a nuclear reaction process.
Specifically, the neutron production rate and neutron loss rate during the nuclear reaction may be obtained from the nuclear reaction process within the storage container 120.
S540: and obtaining an effective proliferation coefficient according to the neutron production rate and the neutron loss rate.
It can be appreciated that the nuclear power station dry-stored spent fuel emergency assessment method provided by the embodiment of the application can obtain the effective proliferation coefficient according to the neutron generation rate and the neutron loss rate.
Specifically, the effective proliferation coefficient (K eff ) The estimation of (2) can be estimated from equation (1).
It can be appreciated that the emergency assessment method for dry stored spent fuel in the nuclear power station provided by the embodiment of the application can provide a reliable assessment means for a storage system, so that the emergency assessment method can keep safe and stable operation under various working conditions.
Fig. 5 is a schematic diagram of a dry stored spent fuel emergency assessment system 20 for a nuclear power plant according to an embodiment of the present application. As shown in fig. 5, the nuclear power plant dry stored spent fuel emergency assessment system 20 includes at least the following: a disaster information acquisition module 21, a risk assessment module 22, a radiation dose acquisition module 23, an effective proliferation factor acquisition module 24 and an execution module 25.
It is understood that the nuclear power plant dry-stored spent fuel emergency assessment system 20 provided in the embodiment of the present application is applied to the nuclear power plant dry-stored spent fuel emergency assessment method as shown in fig. 3 to 4.
In this embodiment, the disaster information obtaining module 21 is configured to obtain information of a natural disaster, and a specific obtaining manner is shown in fig. 1 to 4 and corresponding description thereof, which are not repeated herein.
In the embodiment of the present application, the risk assessment module 22 is configured to obtain the type and risk parameters of the natural disaster according to the natural disaster information, and the specific determination method is shown in fig. 1 to 4 and the corresponding description thereof, which are not repeated herein.
In the embodiment of the present application, the radiation dose obtaining module 23 obtains the radiation dose of the concrete module 100 in response to the risk parameter being higher than the response threshold, and the specific generation manner is shown in fig. 1 to 4 and the corresponding description thereof, which are not repeated here.
In the present embodiment, the emergency management scheme execution module 24 is configured to obtain the effective proliferation factor of the storage container 120 based on the radiation dose. The specific implementation manner and the acquisition manner refer to fig. 1 to 4 and their corresponding descriptions, and are not repeated here.
In an embodiment of the present application, the execution module 25 performs the storage container 120 transfer operation in response to the effective proliferation factor being above the effective proliferation factor threshold. The specific implementation manner and the acquisition manner refer to fig. 1 to 4 and their corresponding descriptions, and are not repeated here.
It should be understood that the sequence number of each step in the foregoing embodiment does not mean that the execution sequence of each process should be determined by the function and the internal logic of each process, and should not limit the implementation process of the embodiment of the present application in any way.
Fig. 6 is a schematic diagram of a terminal device 6 according to an embodiment of the present application. As shown in fig. 6, the terminal device 6 of this embodiment includes: a processor 60, a memory 61 and a computer program 62, e.g. a software program, stored in said memory 61 and executable on said processor 60. The processor 60, when executing the computer program 62, performs the steps described above in the various embodiments of the nuclear power plant dry stored spent fuel emergency assessment method. Alternatively, the processor 60, when executing the computer program 62, performs the functions of the modules/units of the apparatus embodiments described above.
By way of example, the computer program 62 may be partitioned into one or more modules/units that are stored in the memory 61 and executed by the processor 60 to complete the present application. The one or more modules/units may be a series of computer program instruction segments capable of performing specific functions for describing the execution of the computer program 62 in the terminal device 6. For example, the computer program 62 may be partitioned into: software functional unit.
The terminal device 6 may be a computing device such as a desktop computer, a notebook computer, a palm computer, a cloud server, etc. The terminal device 6 may include, but is not limited to, a processor 60, a memory 61. It will be appreciated by those skilled in the art that fig. 6 is merely an example of the terminal device 6 and does not constitute a limitation of the terminal device 6, and may include more or less components than illustrated, or may combine certain components, or different components, e.g., the terminal device 6 may also include input-output devices, network access devices, buses, etc.
The processor 60 may be a central processing unit (Central Processing Unit, CPU), other general purpose processors, digital signal processors (Digital Signal Processor, DSP), application specific integrated circuits (Application Specific Integrated Circuit, ASIC), field-programmable gate arrays (Field-Programmable Gate Array, FPGA) or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, or the like. A general purpose processor may be a microprocessor or the processor may be any conventional processor or the like.
The memory 61 may be an internal storage unit of the terminal device 6, such as a hard disk or a memory of the terminal device 6. The memory 61 may be an external storage device of the terminal device 6, such as a plug-in hard disk, a Smart Media Card (SMC), a Secure Digital (SD) Card, a Flash memory Card (Flash Card) or the like, which are provided on the terminal device 6. Further, the memory 61 may also include both an internal storage unit and an external storage device of the terminal device 6. The memory 61 is used for storing the computer program as well as other programs and data required by the terminal device 6. The memory 61 may also be used for temporarily storing data that has been output or is to be output.
It will be apparent to those skilled in the art that, for convenience and brevity of description, only the above-described division of the functional units and modules is illustrated, and in practical application, the above-described functional distribution may be performed by different functional units and modules according to needs, i.e. the internal structure of the apparatus is divided into different functional units or modules to perform all or part of the above-described functions. The functional units and modules in the embodiment may be integrated in one processing unit, or each unit may exist alone physically, or two or more units may be integrated in one unit, where the integrated units may be implemented in a form of hardware or a form of a software functional unit. In addition, specific names of the functional units and modules are only for convenience of distinguishing from each other, and are not used for limiting the protection scope of the present application. The specific working process of the units and modules in the above system may refer to the corresponding process in the foregoing method embodiment, which is not described herein again.
In the foregoing embodiments, the descriptions of the embodiments are emphasized, and in part, not described or illustrated in any particular embodiment, reference is made to the related descriptions of other embodiments.
Those of ordinary skill in the art will appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware, or combinations of computer software and electronic hardware. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the solution. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present application.
In the embodiments provided in the present application, it should be understood that the disclosed apparatus/terminal device and method may be implemented in other manners. For example, the apparatus/terminal device embodiments described above are merely illustrative, e.g., the division of the modules or units is merely a logical function division, and there may be additional divisions in actual implementation, e.g., multiple units or components may be combined or integrated into another system, or some features may be omitted or not performed. Alternatively, the coupling or direct coupling or communication connection shown or discussed may be an indirect coupling or communication connection via interfaces, devices or units, which may be in electrical, mechanical or other forms.
The units described as separate units may or may not be physically separate, and units shown as units may or may not be physical units, may be located in one place, or may be distributed on a plurality of network units. Some or all of the units may be selected according to actual needs to achieve the purpose of the solution of this embodiment.
In addition, each functional unit in each embodiment of the present application may be integrated in one processing unit, or each unit may exist alone physically, or two or more units may be integrated in one unit. The integrated units may be implemented in hardware or in software functional units.
The integrated modules/units, if implemented in the form of software functional units and sold or used as stand-alone products, may be stored in a computer readable storage medium. With such understanding, the present application implements all or part of the flow of the method of the above embodiments, and may also be implemented by hardware associated with computer program instructions, where the computer program may be stored on a computer readable storage medium, where the computer program, when executed by a processor, implements the steps of the method embodiments described above. Wherein the computer program comprises computer program code which may be in source code form, object code form, executable file or some intermediate form etc. The computer readable medium may include: any entity or device capable of carrying the computer program code, a recording medium, a U disk, a removable hard disk, a magnetic disk, an optical disk, a computer Memory, a Read-Only Memory (ROM), a random access Memory (RAM, random Access Memory), an electrical carrier signal, a telecommunications signal, a software distribution medium, and so forth. It should be noted that the computer readable medium may include content that is subject to appropriate increases and decreases as required by jurisdictions in which such content is subject to legislation and patent practice, such as in certain jurisdictions in which such content is not included as electrical carrier signals and telecommunication signals.
The above embodiments are only for illustrating the technical solution of the present application, and are not limiting; although the present application has been described in detail with reference to the foregoing embodiments, it should be understood by those of ordinary skill in the art that: the technical scheme described in the foregoing embodiments can be modified or some technical features thereof can be replaced by equivalents; such modifications and substitutions do not depart from the spirit and scope of the technical solutions of the embodiments of the present application, and are intended to be included in the scope of the present application.
Claims (13)
1. A nuclear power plant dry stored spent fuel emergency assessment method applied to a dry nuclear horizontal modular storage system, the dry nuclear horizontal modular storage system comprising a concrete module and a storage container, the method comprising:
acquiring information of natural disasters;
acquiring the type and risk parameters of the natural disasters according to the natural disaster information;
acquiring a radiation dose of the concrete module in response to the risk parameter being above a response threshold;
obtaining an effective proliferation factor of the storage vessel based on the radiation dose;
the storage vessel transfer operation is performed in response to the effective proliferation coefficient being above an effective proliferation coefficient threshold.
2. The nuclear power plant dry stored spent fuel emergency assessment method according to claim 1, wherein the obtaining the effective proliferation coefficient of the storage vessel according to the radiation dose comprises:
acquiring a radiation field model of the radiation dose and the storage container;
simulating a nuclear reaction process within the storage vessel according to a radiation field model of the storage vessel;
obtaining neutron production rate and neutron loss rate according to the nuclear reaction process;
and obtaining the effective proliferation coefficient according to the neutron production rate and the neutron loss rate.
3. The nuclear power plant dry stored spent fuel emergency assessment method of claim 1, further comprising, after the acquiring the radiation dose of the concrete module:
obtaining the damage degree of the concrete module;
obtaining damaged part information according to the damage degree;
obtaining damaged part repair sequences according to the damaged part information;
and repairing the damaged part according to the damaged part repairing sequence.
4. The nuclear power plant dry stored spent fuel emergency assessment method of claim 3, further comprising:
obtaining repairability of the damaged part according to the damage degree;
the storage container transfer operation is performed in response to the repairability of the damaged component being below a repairability threshold.
5. The nuclear power plant dry-stored spent fuel emergency assessment method according to claim 1, wherein the types of natural disasters include typhoons, floods and earthquakes.
6. The nuclear power plant dry stored spent fuel emergency assessment method of claim 2, further comprising:
acquiring environmental influence parameters according to the type of the natural disasters and the risk parameters;
when the natural disaster is typhoon, the environment influence parameter is wind speed;
when the natural disasters are of the type of flood, the environmental influence parameters are static water pressure and water flow speed;
when the natural disasters are earthquake, the environment influence parameters are horizontal acceleration and vertical acceleration.
7. The nuclear power plant dry stored spent fuel emergency assessment method according to claim 2, wherein the response threshold is 477 km/h when the natural disaster type is typhoon.
8. The nuclear power plant dry stored spent fuel emergency assessment method according to claim 2, wherein when the natural disaster is of the type of flood, the response threshold is 15.24 meters static water pressure and 4.572 meters per second water flow rate.
9. The nuclear power plant dry stored spent fuel emergency assessment method according to claim 2, wherein the response threshold is 0.3g horizontal acceleration and 0.25g vertical acceleration when the type of natural disaster is an earthquake.
10. The nuclear power plant dry-stored spent fuel emergency assessment method of claim 1, wherein the effective proliferation factor threshold is 0.95.
11. A nuclear power plant dry stored spent fuel emergency assessment system for use in the steps of the method of any one of claims 1 to 10, the system comprising:
the disaster information acquisition module is used for acquiring information of natural disasters;
the risk assessment module is used for acquiring the type and risk parameters of the natural disasters according to the natural disaster information;
a radiation dose acquisition module that acquires a radiation dose of the concrete module in response to the risk parameter being above a response threshold;
an effective proliferation factor obtaining module for obtaining an effective proliferation factor of the storage container according to the radiation dose;
an execution module that performs the storage container transfer operation in response to the effective proliferation coefficient being above an effective proliferation coefficient threshold.
12. A terminal device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, characterized in that the processor implements the steps of the method according to any of claims 1 to 10 when the computer program is executed.
13. A computer readable storage medium storing a computer program, characterized in that the computer program when executed by a processor implements the steps of the method according to any one of claims 1 to 10.
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| CN202311196325.7A CN117391432A (en) | 2023-09-15 | 2023-09-15 | Nuclear power station dry-type stored spent fuel emergency assessment method, system, equipment and medium |
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