104 results about "Nuclear safety and security" patented technology

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 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 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 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 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 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.

The application belongs to the technical field of sealing and particularly relates to a D-shaped sealing ring reinforcing structure for a seawater butterfly valve and a manufacturing process. The sealing ring reinforcing structure comprises a sealing ring body, and a through hole is formed in the sealing ring body. The sealing ring body is annular. Uniformly distributed through holes are formed in the sealing ring body. The sealing ring body comprises a framework fabric and rubber, and the framework fabric has two layers and is nested in the rubber. The application has the beneficial effects that the application has a simple structure, is simple to process and manufacture, has good adhesion between the framework fabric and the rubber, and has no large tearing and damage after installation and use, and the product quality is obviously better than that of the original sealing ring. The application can meet the high reliability use requirements of nuclear power plants and has a positive effect on improving nuclear safety.

The invention relates to the technical field of radiation detection, and provides a radiation detection method and system based on adaptive dead time correction, and the method comprises the steps: obtaining a pulse signal of a radiation detector, and carrying out the preprocessing of the pulse signal, and obtaining initial counting rate data; selecting an initial dead time correction coefficient from a preset correction coefficient library according to a current counting rate range of the initial counting rate data; performing online adjustment on the initial dead time correction coefficient by adopting a self-adaptive algorithm to obtain an adjusted dead time correction coefficient; environment parameters are collected, compensation adjustment is carried out on the adjustment dead time correction coefficient according to the environment parameters, and a compensation dead time correction coefficient is obtained; correcting the initial counting rate data based on the compensation dead time correction coefficient to obtain corrected counting rate data; and converting the corrected counting rate data into radiation dose rate data, and judging whether to trigger an alarm or not according to a preset radiation dose rate threshold value. The accuracy and reliability of radiation detection in the fields of nuclear safety monitoring, emergency response and the like are improved.

The invention provides an automatic execution method and device for digital regulations of a nuclear power plant, equipment and a medium. The method comprises the following steps: acquiring operation data of nuclear power plant equipment from a distributed control system in real time; determining a to-be-executed digital operation instruction according to the operation data; automatically scheduling and executing a plurality of modular operation units corresponding to the digital operation specification; for the currently executed modular operation unit, sending an operation instruction to the distributed control system, and receiving a feedback signal of the distributed control system in response to the operation instruction; according to the feedback signal, whether the current modular operation unit is executed successfully or not is judged, and if yes, the next modular operation unit is automatically triggered to be executed until the digital operation instruction is executed completely. Through modularization and automatic execution, human errors are remarkably reduced, and the nuclear safety level is improved; the regulation execution time is greatly compressed, and the emergency response capability is enhanced; and intelligent closed-loop management is realized by means of fault diagnosis and full-process logs.

The invention belongs to the technical field of nuclear security supervision, and particularly relates to an automatic extraction and entry method for nuclear security supervision document data. Comprising the following steps: step 1, sorting a nuclear security supervision document template and key fields; 2, constructing a nuclear security supervision document intelligent extraction model; and step 3, automatically inputting data and configuring items. The method for automatically extracting and inputting the nuclear security supervision document data has the beneficial effects that text recognition can be carried out on the nuclear security supervision documents of various formats and templates, key information fields are automatically extracted from the documents according to requirements and are filled into a fixed form, and the efficiency is improved. And automatic extraction and entry of nuclear safety supervision data are realized. By developing a corresponding intelligent system, the automatic extraction and entry accuracy of the nuclear safety supervision data can reach 90% or above, the actual application requirements are met, the labor cost can be remarkably reduced, and the obtaining efficiency and accuracy of the nuclear safety supervision data are improved.

The application relates to the technical field of instrument control simulation, in particular to a simulation device and method of a nuclear safety level DCS (Distributed Control System) field control station and a storage medium, the device comprises a plurality of virtual field control stations used for simulating the existing field control station, the virtual field control station comprises a data processing module, a simulation processing module, a virtual board card module and a communication module; the method comprises the following steps: carrying out inter-station communication connection and external station communication connection of the virtual field control station; carrying out data processing of the virtual field control station; creating a virtual board card; processing simulation instructions to complete simulation of the virtual field control station on the existing field control station; various types of board cards are virtually created through the virtual board card module, different types of board cards are individually virtually created, communication in the station and external station communication are realized through the communication module, shared memory is created through the data processing module, data exchange between modules is more efficient, and finally simulation processing is realized through the simulation processing module.

A nuclear purification cabin is arranged in the breeding work ship, a coil pipe is arranged in the nuclear purification cabin from top to bottom, a precipitant solution is connected into the coil pipe, seawater is sent into a nuclear radiation primary detection device by a seawater pump to be detected, after nuclear radiation primary detection is qualified, the seawater enters a breeding cabin through a pipeline, and otherwise, the seawater enters the breeding cabin through a pipeline. The seawater enters the coil pipe again, enters the standing cabin through the coil pipe and waits for secondary detection of nuclear radiation, qualified seawater is fed into the culture cabin after the secondary detection is qualified, and otherwise, the seawater is circulated back to the coil pipe and enters the standing cabin again after being filtered by the coil pipe. According to the invention, nuclear radiation detection is carried out on the seawater entering the culture work ship, and the seawater with the nuclear radiation not exceeding the standard is injected into the culture cabin. In the nuclear purification operation process, no new pollution is generated to seawater, and the nuclear safety of the seawater in the culture cabin is ensured. And sediments formed by radionuclides are independently and specially stored, and are treated after the breeding work ship arrives at the shore, so that extra nuclear pollution is not caused.

The invention discloses a concrete containment post-accident protection structure which is arranged at a construction joint between two adjacent concrete structures and comprises a blocking component, the blocking component is of a continuous strip-shaped structure, the axial extension direction of the blocking component is consistent with the trend of the construction joint, and in the cross section structure of the blocking component, the cross section of the blocking component is provided with a plurality of cross sections. The blocking structure is provided with a blocking section and at least one anchoring section, the anchoring section is embedded in the concrete structure and forms mechanical interlocking with the concrete structure, and the blocking section extends from the concrete structure embedded in the anchoring section to the construction joint and is connected to the concrete structure on the other side so as to block the construction joint to form the protection structure. According to the protection structure, the closeness of the containment is effectively improved through reasonable layout, so that the leakage condition of radioactive substances is reduced or avoided, and time is won for handling nuclear safety problems after accidents. The invention further provides an arrangement method of the concrete containment post-accident protection structure and the concrete containment.

The invention discloses a neutron source based on an FRC linear magnetic confinement nuclear fusion device, and relates to the technical field of fusion devices. The neutron source comprises a vacuum chamber for providing a vacuum environment for fusion reaction; the magnet system is arranged outside the vacuum chamber and is used for ionizing gas in the vacuum chamber and generating fusion reaction; the neutron extraction system is arranged in the fusion reaction generation area of the vacuum chamber and is used for extracting epithermal neutrons; the neutron lead-out system comprises a neutron lead-out channel, a shielding and reflecting device and a filter, the shielding and reflecting device is arranged outside the lead-out channel and used for shielding and reflecting neutrons, and the filter is arranged in the neutron lead-out channel and used for filtering fast neutrons, thermal neutrons and photons; the neutron source provided by the invention has the advantages of higher neutron yield, simple and compact structure, effectively reduced overall device volume, low construction and maintenance cost and small nuclear safety prevention and control pressure, and can be used in various fields of medical treatment, scientific research, military industry and the like.

The invention discloses a dynamic encryption bus communication method and system for nuclear security level software, and the method comprises the steps: monitoring the operation data of each to-be-monitored part in a nuclear facility through each monitoring sensor in the operation process of the nuclear facility; the key generator generates a real-time key according to a preset dynamic key generation algorithm, and transmits the real-time key to each monitoring sensor and the analysis display unit; each monitoring sensor encrypts each operation data based on the real-time secret key to generate ciphertext data and transmits the ciphertext data to an analysis display unit through a bus; and decrypting by software in the analysis display unit to obtain decrypted data, and analyzing and displaying the nuclear security level of the nuclear facility based on the decrypted data. According to the method, the real-time secret key suitable for running data real-time communication transmission is generated through the preset dynamic secret key generation algorithm, and the real-time secret keys between the monitoring sensors are different, so that the problem that the secret keys are easy to leak and attack is avoided, and the safety and the reliability of communication transmission are integrally improved.