132 results about "Nuclear safety and security" patented technology

The invention discloses an automatic generation method and system for an electrical principle design drawing of a nuclear safety level DCS cabinet, and relates to the technical field of nuclear power instrument control, and the method comprises the steps: carrying out the modeling of the electrical principle design process of the nuclear safety level DCS cabinet; associating the model of the nuclear security level DCS cabinet electrical principle design process with the input information; the method comprises the following steps of: according to a nuclear security level and classification of DCS cabinet electrical principle design process modeling, making a page macro for each graph page; and according to the model of the electrical principle design process of the nuclear security level DCS cabinet, specific input of a nuclear security level DCS project to be designed is analyzed, and corresponding required page macros are called for batch drawing, so that automatic generation of the electrical principle design drawing of the nuclear security level DCS cabinet is completed. According to the method, the automatic generation of the electrical principle design drawing of the nuclear safety level DCS cabinet is efficiently and accurately realized, the workload in the DCS engineering hardware design process is reduced, the design efficiency is improved, and meanwhile, human errors are reduced.

The invention discloses a nuclear safety simulation verification method and device based on digital twinning and a medium, and relates to the technical field of nuclear engineering and digital twinning, and the method comprises the steps: training a physical information neural network based on a digital twinning initial model in combination with a nuclide transport equation and a thermal hydraulic equation, and outputting a nuclear safety multi-field simulation result; based on a nuclear safety multi-field simulation result, establishing a space-time diagram structure, extracting dynamic evolution characteristics by using a space-time diagram convolutional network, and outputting a nuclear accident propagation path and a risk distribution diagram; according to the method, the space-time diagram structure is constructed, the space-time diagram convolutional network is utilized to extract the dynamic evolution characteristics, the nuclear accident propagation process is modeled as cascade response in the space-time domain, and the reliability of the nuclear accident propagation process is improved. And the accuracy, the foresight and the intelligent level of nuclear security simulation verification are improved.

The invention provides a shell-and-tube phase change heat storage system for a nuclear reactor containment and a nuclear accident heat energy management method, and belongs to the technical field of nuclear safety engineering and heat energy storage. The problems that an existing shell-and-tube heat reservoir is designed for industrial waste heat recovery and is not suitable for nuclear accidents, and the internal space structure of a containment is complex and limited are solved. The heat storage units are distributed in parallel, and each heat storage unit comprises a shell and a plurality of heat exchange tube bundles arranged in the shell; the heat storage unit has an interchangeable heat storage medium arrangement mode which comprises the first mode that the space in the heat exchange tube bundle is filled with a phase change material, and accident steam flows through a shell side channel between the shell and the heat exchange tube bundle; in the second mode, the shell side space between the shell and the heat exchange tube bundle is filled with the phase change material, and accident steam flows through an in-tube channel of the heat exchange tube bundle; and the accident steam passively flows through the channel which is not filled with the phase change material under the driving of the pressure difference. The method is used in the phase-change heat storage field.

The utility model discloses a phased array ultrasonic testing technology verification test block, which comprises a test block body made of the same material as a target product to be tested, the test block body is arranged in a shape of the target product, a welding seam is arranged on the test block body, the welding seam is formed by adopting the same welding process as the target product, and the test block body is made of a stainless steel material. The specification and the excess weld metal of the welding seam are consistent with those of a target product; welding defects are arranged on the welding seam, and the welding defects comprise one or more combinations of an upper surface groove, a lower surface groove, a longitudinal crack, a transverse crack, incomplete fusion, incomplete penetration, a strip-shaped defect, a circular defect and slag inclusion. According to the utility model, the test block body and the welding defects thereof are designed, so that the manufactured test block body can be used for verifying the accuracy, detectability and reliability of a phased array ultrasonic inspection technology instead of a ray inspection technology in the manufacturing and mounting process of nuclear safety level equipment, and the nuclear safety is ensured.

The invention relates to the field of post-accident gamma dose rate measurement, and provides a post-accident gamma dose rate dynamic measurement method and system based on multi-detector fusion, and the method comprises the steps: obtaining original signal data and environment parameter data; processing the original signal data, the environmental parameter data, the accumulated radiation dose and the displacement damage energy by adopting a deep learning network to obtain corrected signal data; processing the correction signal data and the environmental parameter data through a time sequence prediction network to obtain a dynamic weight distribution result of each detector; processing the correction signal data and the dynamic weight distribution result based on a self-calibration confidence evaluation network to obtain a confidence evaluation result; and processing the correction signal data, the dynamic weight distribution result and the confidence evaluation result through a weighted fusion algorithm to obtain a dynamic measurement result of the gamma dose rate after the accident. According to the invention, high-precision dynamic measurement, real-time damage compensation and nuclear safety level reliability evaluation of the gamma dose rate after an accident are realized.

The invention discloses a parameter optimization method and system based on an agent model and multi-algorithm gradient collaboration, and relates to the technical field of nuclear engineering and nuclear security, and the method comprises the steps: firstly determining a nuclear facility parameter combination, carrying out the high-fidelity calculation through a Monte Carlo program to obtain a Keff value, and constructing a training set; training a micro-proxy model capable of predicting a Keff value and gradient information through a feedforward neural network in combination with a back propagation algorithm, taking the micro-proxy model as a target function, taking the minimum absolute error of a Keff predicted value and a target value as an optimization target, and generating candidate parameter solutions through global exploration of a hybrid optimization algorithm; and an optimal parameter combination candidate solution is obtained through gradient-assisted local optimization, and finally, through Monte Carlo program verification, if the error reaches the standard, the optimal parameter combination candidate solution is used as a final parameter combination solution. The problem that a parameter optimization method in the prior art cannot give consideration to calculation efficiency and precision is solved.

The invention particularly relates to a large sodium-cooled fast reactor power station, which belongs to the technical field of sodium-cooled fast reactors, and comprises a plurality of sodium-cooled fast reactor units and an auxiliary system shared by the sodium-cooled fast reactor units, and each sodium-cooled fast reactor unit comprises a sodium-cooled fast reactor, a main heat transmission system, a power conversion system, an accident waste heat removal system and an energy storage system; the sodium-cooled fast reactor is arranged in a reactor building; the sodium-cooled fast reactor comprises a reactor pit, a containment vessel in the reactor pit and a reactor body in the containment vessel, and is constructed through the following steps that the reactor pit, the containment vessel and the reactor body are constructed in parallel, the reactor body is loaded into the containment vessel after the containment vessel and the reactor body are constructed, the reactor body is modularly manufactured, the containment vessel is a capsule type small steel containment vessel, and the containment vessel is a capsule type small steel containment vessel. The pile pit is built by concrete; and integrally pushing the containment and the reactor body in the containment into a reactor pit. While the nuclear safety and the industrial safety are improved, the economical efficiency of the sodium-cooled fast reactor power station is greatly improved, and the construction period of the sodium-cooled fast reactor power station is greatly shortened.

The invention discloses a nuclear safety level DCS cabinet assembly drawing and cable inventory generation method and system, and relates to the technical field of nuclear power instrument control, and the method comprises the steps: extracting equipment element basic information and connection relation information from a nuclear safety level DCS cabinet electrical wiring schematic diagram, extracting equipment component assembly areas and assembly site number information thereof from the nuclear security level DCS cabinet layout diagram; performing rule matching and classification processing on the extracted information in combination with a preset rule, and performing reconstruction to obtain a relationship between the information; calling a pre-constructed simulation verification mode, and carrying out rechecking verification on the reconstructed information; and generating an assembly drawing and a cable inventory according to the information passing the re-checking verification, and driving to form a file for output. According to the method and the device, automatic generation of the nuclear security level DCS assembly drawing and the cable inventory is efficiently and accurately realized, the manual workload is reduced, human errors are reduced, the design efficiency and accuracy are improved, and the design correctness can be verified.

The invention discloses a multi-stage cascade semantic analysis framework of a nuclear security level control code generation tool, which comprises an input layer, an analysis module layer, an error processing layer and an output layer, and is characterized in that the input layer is used for receiving and preprocessing a control model xml file, verifying a file format and preliminarily checking grammar; the analysis module layer is used for analyzing post grammar, namespace, type, clock, causal relationship and initialized semantic analysis tasks of the file after receiving the analysis request to obtain analysis results; the error processing layer is used for collecting, classifying, positioning and report generating various error information appearing in the analysis module layer; and the output layer is used for generating and outputting a standardized analysis report and an optimization suggestion. And a pipelined cascade structure is adopted, so that efficient semantic analysis is realized. Through an innovative error processing mechanism and an optimization strategy, the analysis efficiency and accuracy are remarkably improved, and a reliable guarantee is provided for software development of a digital instrument control system of the nuclear power station.

The invention relates to a nuclear power system equipment nuclear safety performance evaluation method, which comprises the following steps of: obtaining a complete system list of a power plant, and screening the system list according to a nuclear safety function correlation condition to obtain a function list meeting a nuclear safety function requirement; classifying the function list based on the operation state to obtain a category system classification of the nuclear safety related system equipment meeting the operation state classification standard; performing performance index making according to the category classification to obtain a performance index making result of the nuclear safety related system equipment; and performing nuclear safety performance evaluation on the nuclear safety related equipment in the preset time period according to the performance index formulating result to obtain a nuclear safety performance evaluation result in the preset time. Through systematic equipment screening and classification, scientific and reasonable performance index formulating and dynamic performance evaluation based on actual operation data, the nuclear safety performance of the nuclear safety related equipment in the preset time period is evaluated; and refined evaluation of nuclear power plant system equipment nuclear safety performance is realized.

This invention relates to the field of nuclear safety equipment testing technology. It provides a method for optimizing parameters in accelerated reliability testing of nuclear safety-grade valves. The method involves the following steps: establishing a correlation model between accelerated stress and life parameters; calculating the acceleration factor and formulating an initial test plan; deriving the theoretical sample size based on the success-failure test method combined with confidence requirements; constructing an extended coefficient table using the range-extended test method to optimize test parameters; generating multiple accelerated test plans through chi-square distribution verification; eliminating plans that do not meet the life characteristic threshold; determining the optimal sample size, number of failures, and test cycle through comprehensive test cost and risk analysis; and finally outputting a complete test plan including the action interval time. This method solves the problems of limited test samples, insufficient failure data, low confidence levels, and difficulty in adapting accelerated models in existing high-reliability valve technologies.

The invention discloses a hot standby redundancy switching method and system based on credible state strategy judgment and a medium. The method comprises the following steps: acquiring DCS input data; data verification is carried out on DCS input data based on a redundant communication network between the master controller and the slave controller; based on a trusted state strategy synchronization mechanism, performing service data synchronization on the verified DCS input data between the master controller and the slave controller; the service data synchronization comprises master-slave controller credible state strategy data synchronization and master-slave controller service data synchronization; when the master controller diagnoses a self-diagnosis fault or a communication fault, whether the master controller and the slave controller need to be switched or not is judged by combining the state of the slave controller; if switching is needed, according to the fault state, master-slave arbitration is carried out based on a preset switching condition truth table, and switching of master-slave controller state identification is completed. According to the invention, full-station communication fault detection and master-slave switching of the domestic nuclear safety level DCS field control station are realized, and the safety of the domestic nuclear safety level DCS is improved.

The invention provides a test device and method for fission source item release in an irradiated fuel element, and relates to the technical field of nuclear safety fission product source item tests. The test device comprises a reaction kettle, a water circulation system and a pressure stabilizing system, the water circulation system comprises a water tank, a make-up pump, a surge tank and a preheater which are sequentially connected through pipelines, the preheater is communicated with the feeding end of the reaction kettle, the surge tank is communicated with the discharging end of the reaction kettle, and a circulating pump is further arranged at the discharging end of the reaction kettle; the pressure stabilizing system comprises a gas steel cylinder and a filter which are sequentially connected through a pipeline, and the filter is respectively communicated with the pressure stabilizing tank and the reaction kettle; an ion exchange bypass and a water condensation bypass are further arranged on a connecting pipeline of the pressure stabilizing tank and the reaction kettle, an ion exchange column is arranged on the ion exchange bypass, and a condenser is arranged on the water condensation bypass. Dynamic source item tests of radionuclides can be carried out, so that nuclide release behavior researches of irradiated fuel elements in various element forms can be realized.

The invention belongs to the technical field of nuclear safety, and particularly relates to a nuclear power plant item quality management method comprising the following steps: obtaining an input item list; identifying the type of each item on the item list by using a pre-trained probabilistic safety evaluation model of the nuclear power plant, and evaluating the risk guidance type safety level of the item; wherein the items of which the types and the risk guidance type security levels are identified are at least pre-modeled in a probabilistic security evaluation model; the risk guidance type security level comprises a security level and high security importance, a non-security level and high security importance, a security level and low security importance, and a non-security level and low security importance; and based on the type of the item, matching a corresponding quality management requirement from a quality management requirement database of the risk guidance type security level corresponding to the item, and managing and maintaining the item according to the quality management requirement. The safety of the nuclear power plant can be considered, objective economic benefits are brought, and safe, stable and continuous operation of the nuclear power plant is guaranteed.

The application discloses a kind of digital fuel physics supervision method and system suitable for heavy water reactor, it is related to nuclear reactor fuel management technical field, system includes data acquisition module, document scale calculation interface, system management module and central processing module, central processing module configuration basic data, new fuel, FCO, spent fuel, dry storage area management unit.Method is standardized by data acquisition, whole-process digital control, dynamic monitoring and tracing three steps, realize fuel full life cycle closed-loop management.System adopts PDA to cooperate bar code / RFID to realize entity information acquisition and offline synchronization, constructs hierarchical correlation model, with new fuel isolation control, FCO closed-loop approval, spent fuel transfer verification, fine authority control and other functions, can improve management efficiency, reduce human error, strengthen data tracing and operation standardization, guarantee nuclear safety, provide support for management decision, suitable for heavy water reactor fuel physics supervision and whole-process management.

The invention discloses a nuclear reactor neutron flux prediction method based on global conservation constraint, and belongs to the nuclear reactor physics and machine learning crossing field, and the method comprises the following steps: constructing a depth operator network model based on global neutron conservation constraint; collecting solution data of a neutron transport equation or a neutron diffusion equation under different parameters, constructing a training data set, and training the depth operator network model to obtain an optimal model weight; and initializing the depth operator network model by using the optimal model weight, applying the depth operator network model to a neutron transport equation or a neutron diffusion equation under different parameters for solving, and predicting neutron flux distribution in a corresponding region of the nuclear reactor. According to the method, the physical constraint term for describing the global conservation of neutrons is introduced, so that the accuracy and the physical consistency of the DeepONet network for predicting the neutron transport or neutron diffusion solution can be remarkably improved, the generalization ability and the robustness of the model can be enhanced, and the method is particularly suitable for meeting the rapid and high-precision calculation requirements in the fields of reactor design, reactor core analysis and nuclear safety evaluation.

The invention discloses a method and a device for determining an intelligent control scheme of a heating and ventilation system of a nuclear power plant. The method comprises the following steps: determining functional requirements of each plant based on a heating and ventilation requirement table of each plant room of the nuclear power plant; determining the configuration condition of the heating and ventilation system in each plant according to the functional requirements; determining controlled equipment and monitoring point requirements corresponding to the heating and ventilation system according to the configuration condition; according to the functional requirements of the plant, the controlled equipment corresponding to the heating and ventilation system and the monitoring point requirements, generating a regular alternation control scheme of the configuration of the heating and ventilation system corresponding to each plant, an intelligent control scheme of the kernel safety equipment of the heating and ventilation system and the like; through the method and the device, automatic control of the heating and ventilation system can be realized, the reliability of the system is improved, and the system maintenance pressure is reduced.

The invention belongs to the technical field of nuclear power station operation management and nuclear safety, and relates to an automatic scheduling method and system for nuclear emergency duty, and the method comprises the steps: obtaining multi-source data related to nuclear emergency duty, and carrying out the fusion coding of heterogeneous features in the multi-source data through employing a multi-head attention mechanism; on the basis of the encoded features, a deep reinforcement learning model is adopted, and an initial scheduling scheme is generated under the condition that multiple types of constraints are met; the deep reinforcement learning model is realized based on a DQN network; and performing conflict optimization and multi-dimensional automatic verification on the initial scheduling scheme based on a tree search algorithm, and outputting a final scheduling scheme. By adopting the method, the dynamic response and fairness are obviously improved; the scheduling efficiency and the compliance are greatly improved; and the system elasticity and stability are obviously enhanced.

The invention discloses a nuclear power station dragon scale platform safety level DCS configuration maintenance downloading method, system and device and a medium. The method comprises the steps of obtaining system parameters of a safety level distributed control system; according to the system parameters, the security-level distributed control system is divided into a shutdown protection group and a special sequence; the shutdown protection group sequentially performs configuration maintenance downloading work of the distributed control system within a set time threshold range, and after the downloading work is completed, a time system is recovered and a state is verified; and specifically setting a sequence to check the state of the equipment, disconnecting the control electric isolation, then carrying out the configuration maintenance downloading work of the distributed control system, and after the downloading work is completed, recovering power supply and verifying the state. According to the invention, the risk of the security-level distributed control system can be controlled in a decentralized manner, the overall downloading risk level is reduced, the equipment misoperation probability is effectively avoided, and the problems of uncontrollable risk, abnormal equipment linkage and low operation efficiency in the traditional offline updating of the nuclear security-level digital control system are solved.

The present invention relates to the field of nuclear building seismic performance, and discloses a method, device and storage medium for calculating the seismic performance of nuclear safety buildings. The method comprises: obtaining the initial load-resistance ratio of the most unfavorable component of the building to be detected; based on the incremental dynamic analysis method, respectively calculating the corresponding failure probability values ​​of multiple nuclear safety buildings under the original design earthquake motion parameters under earthquake waves of different amplitudes; obtaining a first adjustment coefficient based on the failure probability value; sampling and testing all components in the building to be detected, and obtaining a second adjustment coefficient based on the sampling ratio and test results of the building to be detected; obtaining a third adjustment coefficient based on the natural vibration period of the building to be detected and the natural vibration period of the equipment support structure in the building to be detected; generating an earthquake evaluation result based on the initial load-resistance ratio, the first adjustment coefficient, the second adjustment coefficient and the third adjustment coefficient. The method disclosed in the present invention can accurately calculate the seismic performance of a building under different earthquake motion parameters.

The invention relates to a nuclear security supervision data migration method and device, computer equipment, a storage medium and a computer program product. The method comprises the steps of determining a to-be-migrated field corresponding to a to-be-migrated data form in response to a data migration instruction for the to-be-migrated data form corresponding to the nuclear security supervision system; determining a first data classification result of the to-be-migrated field and a second data classification result of the field value of the to-be-migrated field; determining a target data classification result of the to-be-migrated field according to the first data classification result and the second data classification result; determining a migration classification template corresponding to the to-be-migrated field according to the target data classification result; the migration classification template is used for representing a mapping relation of the to-be-migrated field between the nuclear security supervision system and a target nuclear security supervision system; and according to the migration classification template, migrating the to-be-migrated field from the nuclear security supervision system to the target nuclear security supervision system. By adopting the method, the data migration efficiency can be improved.

A system for containing a nuclear reactor is disclosed. The system includes a nuclear containment structure comprising a plurality of metallic rings stacked axially to form the nuclear containment structure. The nuclear containment structure includes a central chamber that comprises a volume enclosed by the inner wall of each of the plurality of metallic rings, and also includes a plurality of auxiliary chambers. The central chamber encloses a nuclear reactor vessel, wherein the inner wall of the plurality of metallic rings is flush with the nuclear reactor vessel. Cooling channels also exist within the nuclear containment structure. The nuclear containment structure is configured to shield the nuclear reactor vessel from kinetic events originating external from the nuclear containment structure and to shield an external environment from kinetic events within the nuclear reactor vessel.

The invention discloses a function distribution method and system of a nuclear safety level digital instrument control system and a medium. Relates to the technical field of nuclear safety level instrument control design. The method is improved on the basis of the traditional technology, an FD / SAMA graph is analyzed to construct a same-level system interface graph and an internal system relation graph on the basis of meeting function dispersion and diversity design, and the internal system interface graph and the internal system relation graph are constructed on the basis of a same-class merging rule, a priority rule and a mutual exclusion rule. Performing function distribution on each site of the nuclear security level digital instrument control system by combining a same-level system interface diagram and an internal system relation diagram, performing system operation calculation on each group of function distribution schemes, and screening out an optimal function distribution scheme; the function distribution design is optimized, the coupling between systems is reduced, the response time, the load rate and the margin of each subsystem are ensured to meet the requirements, the design quality is improved, the design efficiency is improved, the later design iteration is reduced, and the design period is shortened.

The application discloses an experimental test and evaluation method for simulating breakage of a nuclear fuel rod and escape characteristics of fission products, which comprises consideration of similarity criteria, and ensures that the cylindrical geometry of the broken fuel rod can simulate the flow characteristics of the flow field near the break along the axial direction of the cylindrical surface; and the flow similarity in the experimental section is realized by Re>10 5 The flow field enters the self-modification area; the critical break diameter is determined based on the blocking flow theory; the specific experimental conditions are determined by single variable control processing of multiple factors; the release rate of fission products per unit time and the escape rate of fission products finally entering the coolant are divided into two experiments of fuel rod constant internal pressure and fuel rod sealing for measurement; and high-confidence uncertainty evaluation is carried out by using A and B two types of evaluation components; and the experimental results are used to fit the fission product escape rate coefficient model. The application solves the problems of poor reliability of experimental extrapolation, blind selection of working conditions and incomplete evaluation system, and provides high-precision benchmark data for nuclear safety analysis programs.

The present invention discloses a method for evaluating the concrete structure performance of existing nuclear safety-related plants, which includes the following steps: (1) Divide the existing nuclear safety-related plants into structural areas with different seismic requirements based on the failure safety risk of the plants, and formulate different structural review standard requirements; (2) Conduct durability evaluation and strength analysis on the plants to determine the current mechanical properties and load-bearing capacity of the structural components of the existing plants; (3) Determine the numerical calculation model of the existing nuclear safety-related plants, apply load effects to the model, and then conduct performance simulation calculations; (4) Macroscopically evaluate the overall seismic performance of the existing nuclear safety-related plants according to the results of the performance simulation calculations. The method in the present invention maximally applies the concept of structural performance design, enabling the existing plants to continue to be put into use as much as possible, and playing a promoting role in improving the structural design technology of nuclear safety-related plants. This method is technologically advanced, safe and reliable, and simple to implement.

The application discloses a nuclear safety level display control device based on optical fiber networking, and relates to the field of digital control systems of nuclear power plants. The nuclear safety level display control device serves as a node of multiple independent optical fiber networks. Each optical fiber network comprises multiple safety level control stations and multiple nuclear safety level display control devices. The nuclear safety level display control device comprises a control module, a data processing module, a fault diagnosis module, a display touch module and multiple optical fiber communication modules. The control module is connected with the display touch module. The data processing module is connected with the control module and each optical fiber communication module. Each optical fiber communication module is connected with the data processing module and the optical fiber of one optical fiber network. The fault diagnosis module is connected with the control module, the data processing module and each optical fiber communication module. The nuclear safety level display control device transmits data through high-speed optical fiber networking technology, meets the safety level requirement, improves the data transmission rate, and avoids data delay reception and loss.

The invention discloses a compact high-resolution epithermal neutron resonance absorption spectrum method and a compact high-resolution epithermal neutron resonance absorption spectrum device in the technical field of nuclear physics application, and aims to solve the problems of large size, high cost and limited application of a traditional epithermal neutron source. The method comprises the following steps: generating an epithermal neutron source with high repetition frequency and microsecond-level pulse by using a kilohertz femtosecond laser, accelerating an electron beam through a laser plasma wake field, bombarding a metal target to generate fast neutrons, and processing the fast neutrons through a polyethylene body to obtain an epithermal neutron energy spectrum with ultrahigh energy resolution; the device comprises a femtosecond laser, a vacuum target chamber, a supersonic nozzle, a high-atomic-number metal target, polyethylene, a collimator, an EJ-420 detector and other key components, and is compact in design, convenient to move and convenient for multi-scene application. The technology can realize accurate diagnosis of the type and abundance of nuclides in nuclear fuel and nuclear waste and non-contact temperature measurement in a special environment, and has important nuclear safety and nuclear guarantee application values.

The invention discloses a nuclear facility pipeline monitoring data sampling uniformity correction method and a corresponding system. The method comprises the steps that modeling software is used for conducting modeling and mesh generation on a target pipeline of the nuclear facility, a space mesh model is imported into fluid mechanics software, and simulation is conducted based on the set model and parameters according to different working conditions; based on the local flow field and nuclide concentration distribution in the target pipeline in the simulation result, determining a numerical simulation result of the uniform mixing point meeting the set speed and concentration standard; under the same working condition, multiple pieces of actual monitoring data of an existing sampling opening in the target pipeline are obtained; performing comparative analysis on the numerical simulation result and a plurality of actual monitoring data, and establishing a sampling uniformity correction model; and acquiring current monitoring data of the existing sampling port, and substituting the current monitoring data into the sampling uniformity correction model for correction to obtain uniformly sampled monitoring data. Therefore, it is ensured that the corrected monitoring data are more real, and real, reliable and accurate monitoring data are provided for subsequent nuclear safety supervision.

The invention discloses a reinforced concrete boric acid corrosion warning method, device and equipment, a medium and a product, and relates to the field of civil engineering materials and nuclear engineering, and the method comprises the following steps: receiving reinforced concrete information of a nuclear power plant; based on the reinforced concrete information, the boric acid environment corrosion information of the reinforced concrete of the nuclear power plant is detected in real time through a pre-constructed final prediction model, and when the reinforced concrete corrosion information reaches an alarm threshold value, alarm information is generated and sent to corresponding maintenance and management personnel. Therefore, the problem of nuclear safety accidents caused by the fact that the boric acid corrosion degree of the reinforced concrete cannot be predicted in combination with the actual use condition of a nuclear power plant is solved, and the accuracy of the boric acid corrosion alarm of the reinforced concrete is improved.

A structure and process for containing a nuclear reaction is disclosed. The structure and process may involve a nuclear containment structure including a plurality of metallic rings stacked axially to form the nuclear containment structure, the nuclear containment structure being configured to: mitigate, by using a physical barrier, the movement of radionuclides from inside a containment structure to a surrounding space; shield, by varying the alloy properties throughout the containment structure, an exterior of the containment structure from radiation produced inside of the containment structure; regulate, by transferring thermal energy, a temperature within the containment structure; regulate, by storing thermal energy, the temperature within the containment structure; shield, components within the nuclear containment structure from kinetic events external to the nuclear containment structure; and shield, the external environment, from kinetic events within the nuclear containment structure.