18 results about "Nuclear safety and security" patented technology

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 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 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.

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.

This invention discloses a biomimetic smartphone integrated system based on a nuclear battery, including a smartphone intelligent nuclear energy system; a biomimetic smartphone screen; a biomimetic smartphone casing; and an AI intelligent control module. The smartphone intelligent nuclear energy system adopts an isotope-powered and closed-loop safety protection architecture. Its radiation shielding system uses an integrated transducer-shield composite structure and topological materials, which can recover secondary energy from escaping beta rays without reducing protection standards, thereby supplementing and increasing the overall output power density of the device, achieving continuous and stable power supply and full-link nuclear safety protection. The AI ​​intelligent control module communicates and coordinates with the smartphone intelligent nuclear energy system, the biomimetic smartphone screen, and the biomimetic smartphone casing throughout the entire process. This invention not only breaks through the battery life ceiling of mobile terminals but also constructs a multi-level, full-link nuclear safety protection system, which is compatible with existing smartphone mass production systems and user habits, and features ultra-long battery life, high safety, low power consumption, and environmental friendliness.

The invention relates to the field of nuclear safety, in particular to an online monitoring and online protection calculation method and system suitable for a large pressurized water reactor core. The method comprises the following steps: selecting a typical operation state parameter combination according to the range of key operation state parameters of a reactor core; receiving real-time measurement data of the operation state parameters, calculating a plurality of sets of intermediate coefficients based on the reactor core state at the current moment t0 according to the selected operation state parameter combination, forming an intermediate coefficient library containing the plurality of sets of intermediate coefficients, and then carrying out rapid protection calculation on the formed intermediate coefficient library; meanwhile, a set of intermediate coefficients is calculated based on the reactor core state at the current moment t1 according to the current running state parameters measured in real time, and after calculation is completed, rapid monitoring calculation is conducted through the set of intermediate parameters. The system comprises a measuring system, an upper layer unit and a lower layer unit, the upper layer unit comprises a fine tracking calculation module and a rapid monitoring calculation module; and the lower layer unit comprises a rapid protection calculation module. According to the method, accurate and efficient calculation of the key safety parameters of the online protection system is realized, and the unit operation flexibility and economy of the pressurized water reactor core nuclear power plant are improved.

This application provides an intelligent verification system, method, medium, and electronic device for nuclear power plant isolation management, relating to the field of nuclear power technology. The intelligent verification system for nuclear power plant isolation management includes a database module, a rule management module, a process design module, a review engine module, and a user interaction and feedback module. It can introduce a rule engine during the isolation management process creation stage, automating the review based on target isolation management rules associated with the process. This improves process compliance from the source, as well as the real-time nature, accuracy, and efficiency of compliance verification, overcoming the limitations of traditional reliance on manual experience and post-event remediation, and preventing nuclear safety accidents caused by process defects.

This invention discloses a method for preparing GaAs semiconductor crystals and their applications, belonging to the field of compound semiconductor material preparation. The method includes: axially pressing ground GaAs powder to obtain a green compact; placing the green compact in a vacuum tube furnace; heating under vacuum and applying an electric field to trigger a flash combustion reaction; and finally obtaining a dense GaAs polycrystalline material. Compared with traditional melt and vapor phase methods, this invention can complete crystal preparation at lower temperatures and in a very short time, significantly reducing energy consumption and production costs, shortening the preparation cycle, and requiring simple equipment and convenient operation. The resulting GaAs crystals have few internal defects, uniform resistivity, and excellent carrier transport performance, effectively suppressing dark current and noise levels in devices. They are suitable for room-temperature X-ray radiation detectors and have broad application prospects in nuclear safety monitoring, high-energy physics experiments, and space astronomical observation.

The application discloses a kind of high temperature gas cooled reactor liquid nitrogen daily evaporation rate test method and device, belong to high temperature gas cooled reactor nuclear safety guarantee technical field.First, the multi-stage valve isolation is executed to liquid nitrogen supply and storage system, and the isolation reliability is guaranteed by double confirmation mechanism of system state and mechanical locking;Subsequently, the vacuum degree of interlayer of storage tank is detected using nuclear level calibrated vacuum gauge, and repair is carried out if it does not satisfy preset threshold;When filling liquid nitrogen, intermittent injection is carried out using nuclear level cryogenic stainless steel hose, and bottom liquid discharge valve purging is matched, until the purity of exhaust gas reaches standard after filling to target liquid level;Finally, after the specified reference standing period containing eliminating initial gasification disturbance, daily evaporation rate is calculated according to liquid level change and geometric parameter model.The present application ensures the rigor of test and the repeatability of result through standardized process and multiple verification.

Methods, systems, and apparatus, including computer programs encoded on a computer storage medium, for controlling magnetic confinement devices using a controller neural network trained via reinforcement learning. Examples of control systems for magnetic confinement devices are described herein that utilize the controller neural network for optimizing heat and particle flux deposition of diverted plasma configurations. The controller neural network is trained on a model of the magnetic confinement device to establish diverted configurations that eject heat and particle flux onto one or more divertors while maintaining temperatures over plasma-facing components within allowable safety bounds. Implementations of the control systems described herein can be applied to controlled thermonuclear fusion, advanced plasma research, nuclear safety tests, among other applications.

This invention discloses a frequency regulation and peak shaving coordinated control system and method for a hybrid nuclear energy system with source-grid-load-storage, belonging to the field of power system operation and control technology. It includes a nuclear power unit, a wind and solar power generation module, a composite energy storage module, a tiered load unit, and a coordinated controller. Wind and solar power generation and chemical battery energy storage are aggregated via a DC aggregation bus, and after conversion, they are connected to the AC bus along with the nuclear power unit. The molten salt energy storage unit is coupled to the secondary loop side of the nuclear power unit. The coordinated controller collects system data and uses model predictive control strategies for multi-timescale optimization: molten salt energy storage is used to achieve thermoelectric decoupling of nuclear energy to meet long-cycle peak shaving needs, while chemical battery energy storage is used to smooth DC bus fluctuations to respond to short-cycle frequency regulation needs. This invention effectively isolates the impact of renewable energy fluctuations on the nuclear power baseload, significantly improving the grid flexibility and renewable energy absorption capacity while ensuring nuclear safety.

The application relates to a fuel assembly unloading shielding tank, which comprises a tank body, an accommodating cavity for accommodating a fuel assembly is formed in the tank body, and a through opening and an open end communicated with the accommodating cavity are formed in opposite ends of the tank body along the axial direction; a tank cover is movably connected to the tank body and used for opening or closing the open end; a trigger block is movable relative to the tank body and can be filled in or separated from the through opening; the tank cover opens the open end when the trigger block is separated from the through opening and closes the open end when the trigger block is filled in the through opening. The fuel assembly unloading shielding tank can reduce the radiation risk of workers during fuel assembly unloading, improve operation safety and be beneficial to nuclear safety control.

The application discloses a data conversion and output method and system for CANDU reactor radiation dose simulation, relates to the technical field of nuclear engineering safety analysis and computer simulation, and comprises the following steps: obtaining original dose data in the unit of (Sv / s) / (Bq / m3) in a nuclear safety analysis report, automatically converting the original dose data into dose conversion factors in the unit of (Sv / s) / (individual / m3) based on a decay constant, and performing working condition adaptability correction on the dose conversion factors in combination with at least one of heavy water moderation characteristics, horizontal pressure tube geometric effects and double-loop asymmetric source term distribution characteristics to obtain corrected dose conversion factors; simulating the total number of captured radionuclide atoms, multiplying the total number of captured radionuclide atoms by the corrected dose conversion factors after volume standardization to obtain an instantaneous dose rate, and then performing time integration on the instantaneous dose rate to obtain a cumulative dose, and automatically converting the cumulative dose into an mSv order output, so that the calculation efficiency, simulation accuracy and engineering usability are significantly improved.

The application provides a quality plan control point forced verification method and system integrated in a work order execution process, which comprises the following steps: when a work order is executed to a process step of a bound quality control point, suspending the subsequent operation of the work order in the process step; querying the state of the bound quality control point at a fixed time, verifying the current state of the bound quality control point; if the state of the quality control point in the verification result is "signed", the process blocking is released, and the work order is allowed to enter the next process step; if the state of the quality control point in the verification result is "not signed" or "to be witnessed", the blocking state is continuously maintained. The application has the advantages that: the "skip point" behavior caused by human negligence is completely eliminated, the quality guarantee level of nuclear safety work is greatly improved, the digital deep integration of quality activities and production activities is realized, the process island is eliminated, and the risk of human error is effectively reduced through system guidance and forced constraint.

The present invention relates to the field of nuclear safety, and in particular relates to an online monitoring and online protection calculation method and system applicable to the core of a large pressurized water reactor. The method comprises: on the basis of the ranges of key operating state parameters of a core, selecting a typical operating state parameter combination; receiving real-time measurement data of the operating state parameters; on the basis of the selected operating state parameter combination and the core state at a current moment t0, calculating a plurality of sets of intermediate coefficients so as form an intermediate coefficient library including the plurality of sets of intermediate coefficients; then, using the formed intermediate coefficient library to perform fast protection calculation; meanwhile, on the basis of the current operating state parameters measured in real time and the core state at the current moment t1, calculating a set of intermediate coefficients, and after the calculation is completed, using the set of intermediate parameters to perform fast monitoring calculation. The system comprises: a measurement system, an upper-layer unit and a lower-layer unit, wherein the upper-layer unit comprises a fine tracking calculation module and a fast monitoring calculation module, and the lower-layer unit comprises a fast protection calculation module. The present invention realizes the accurate and efficient calculation of key safety parameters of an online protection system, thereby improving the operational flexibility and economy of a nuclear power plant unit which has a pressurized water reactor core.

The application relates to the cross field of nuclear safety and membrane separation technology, and particularly relates to a ceramic membrane assembly abnormality diagnosis method and system for a nuclear-grade high-temperature dust-containing environment. The method comprises the following steps: S1: acquiring multi-source data of a ceramic membrane assembly, presetting a time acquisition window and a maximum storage time, constructing a coupling memory matrix of the ceramic membrane assembly, and extracting a real-time query feature vector; S2: calculating a transient drift sensitive factor of the ceramic membrane assembly in the query feature vector according to the query feature vector; calculating a real-time scalar sequence of the ceramic membrane assembly and a historical scalar sequence matrix according to the transient drift sensitive factor; and S3: calculating a single-dimensional drift indicator of the query feature vector and the coupling memory matrix according to the real-time scalar sequence and the historical scalar sequence matrix. The application acquires drift compensation through a historical scalar sequence and a real-time scalar sequence, and jointly diagnoses according to the drift compensation and thermal fatigue.