20results about "Nuclear power plant control" patented technology

A pressure control method and a pressure stabilizing control system. The method comprises: acquiring a pressure measurement value and a pressure setting value of a pressurizer (101); determining a pressure deviation value on the basis of the pressure measurement value and the pressure setting value (102); if the absolute value of the pressure deviation value is less than or equal to a first preset value, regulating the charging flow and the letdown flow of a circuit on the basis of the pressure deviation value and the pressure measurement value, so as to control the pressure of the pressurizer (103); and if the absolute value of the pressure deviation value is greater than the first preset value, on the basis of the pressure deviation value, controlling the pressurizer to inflate or deflate so as to control the pressure of the pressurizer (104). The method and the system can improve the pressure stabilizing effects of pressure stabilizing control systems.

The invention belongs to the technical field of nuclear power plant operation control, and particularly relates to a nuclear power plant seawater plate heat exchanger pressure difference and temperature control system and method. An equipment cooling water outlet of the plate heat exchanger is provided with an equipment cooling water thermometer, and a plate heat exchanger bypass pneumatic control valve and a plate heat exchanger differential pressure gauge are arranged between a seawater inlet and a seawater outlet of the plate heat exchanger in parallel. A seawater inlet of the plate heat exchanger is respectively connected with the plate heat exchanger positive flushing inlet pneumatic isolating valve and the plate heat exchanger back flushing outlet pneumatic isolating valve, and a seawater outlet of the plate heat exchanger is respectively connected with the plate heat exchanger positive flushing outlet pneumatic isolating valve and the plate heat exchanger back flushing inlet pneumatic isolating valve. Automatic backwashing of the plate heat exchanger can be achieved, impurities on the seawater side in the plate heat exchanger can be washed away, and the temperature of cooling water of equipment can be controlled to be not lower than the temperature limit value required by design in winter.

This invention discloses a method and system for the operation and maintenance of a shielded pump in a nuclear reactor experimental setup. By monitoring the stress of devices related to the shielded pump within the experimental setup and utilizing a stress assessment model for the shielded pump, the invention enables a clear, comprehensive, and real-time diagnosis of the pump's operating status. This allows for more rational intervention in preventative partial and full disassembly inspections of the shielded pump, enhancing the targeted nature of maintenance interventions, saving manpower and time costs, and increasing the safety and economy of shielded pump operation and maintenance.

This invention discloses a megawatt-class small liquid metal-cooled reactor natural circulation simulation test device and method. The test device simulates fuel rods with a total power output in the MW range, realistically simulating the high-power operation of a small natural circulation liquid metal reactor. A vacuum insulation layer covering the heating section of the simulated fuel rods is installed between the rising channel of the hot pool and the descending channel of the cold pool to block lateral heat conduction and eliminate the "thermal short circuit" problem. A three-loop coupled cooling design of liquid metal-heat transfer oil-water is adopted, ensuring high safety. Furthermore, an air lift auxiliary device and a heat tracing device are integrated. The former effectively breaks the fluid stagnation during the initial startup phase through gas-liquid two-phase disturbance to assist in establishing natural circulation, while the latter ensures that the working fluid remains in a molten state during non-operational or low-power conditions, preventing equipment damage due to working fluid solidification. This invention can accurately simulate the real natural circulation characteristics of a small liquid metal-cooled reactor, combining high precision, safety, and operational reliability.

The present invention relates to a system for determining the operation state of a power plant on the basis of an operation mode. The system may comprise: an operation mode determination device for determining the current operation mode of the power plant by using state information regarding each device in the power plant; a power plant operation state assessment device for assessing the current operation state of the power plant on the basis of the current operation mode; and an interface for providing the current operation state of the power plant to an operator.

The application provides an underwater nuclear power data center system and relates to the technical field of data centers.The system comprises a nuclear energy conversion unit, an electric energy conversion unit, a data center unit and a heat exchange assembly, wherein the nuclear energy conversion unit is used for nuclear reaction; the electric energy conversion unit is connected with the nuclear energy conversion unit, so that the reaction energy of the nuclear energy conversion unit is transmitted to the electric energy conversion unit through a working medium to generate electricity; the data center unit is connected with the electric energy conversion unit and is powered by the electric energy conversion unit, and the data center unit is used for data operation and storage. The nuclear energy conversion unit, the electric energy conversion unit, the data center unit and the heat exchange assembly are integrally designed, so that the heat generated by the operation of the data center unit and the waste heat released by the electric energy conversion unit are uniformly incorporated into the heat load managed by the cooling loop, and are efficiently cooled by the external seawater as an infinite heat sink.

This invention belongs to the technical field of defining the standard requirements for nuclear power plant instrumentation and control systems, specifically relating to a method for defining the granularity of standards for nuclear power plant instrumentation and control systems. It establishes a two-dimensional analysis framework, determining the elements of the first dimension by decomposing them according to the relevant activity types of the system and equipment throughout the entire lifecycle of the nuclear power plant; determining the elements of the second dimension by decomposing them according to the dimensions of typical instrumentation and control system signal flows; integrating the collected information into a coherent standard system, defining specific standards for each activity stage and signal flow link, ensuring seamless integration between them, and ensuring that changes in one area do not negatively impact other areas; establishing a continuous improvement and feedback mechanism, periodically evaluating the effectiveness and applicability of the standards and adjusting them as needed. This invention ensures the reliable and economical operation of nuclear power plant units.

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.

An integrated system for indirect cycle steam heating, comprising: a nuclear module configured to output a first steam; a turbine generator configured to receive the first steam and output a second steam; a heat exchanger configured to receive water, receive at least one of the first steam and the second steam, and transfer heat from at least one of the first steam and the second steam to the water to produce a third steam; a peak heater configured to receive the third steam, transfer enhancement heat to the third steam, and, at least partially based on the transfer, heat the third steam to a temperature above a threshold temperature; an auxiliary heater configured to receive the third steam; and a chemical processing plant configured to receive the third steam and transfer heat from the third steam to chemical substances.

The invention relates to a process for producing a light-water nuclear reactor core, in particular a pressurised-water nuclear reactor (PWR) core, in batch operation at low power density and temperature, comprising weakly 235U-rich, highly poisoned UOX-type fuel assemblies. The invention relates to a process for producing a light-water nuclear reactor core, in particular a pressurised-water nuclear reactor (PWR) core, comprising the following main steps: i / defining a plan for loading the fuel assemblies constituting the core, in accordance with four zones arranged in a three-dimensional pattern that is symmetrical with respect to two orthogonal planes; ii / once the loading plan is defined in accordance with step i / , defining a sequence for controlling the core.

The present application relates to the technical field of nuclear power industry safe operation, and discloses a nuclear power plant operation detection method and device, electronic equipment and storage medium, the method comprises the following steps: obtaining standard operation information of a nuclear power plant; in response to a voice operation instruction for a target device, the voice operation instruction is identified to obtain first operation information, the first operation information comprises first device information and a first set value; at least one nuclear power device comprises the target device; in response to the setting operation on the operation panel of the target device, the panel image of the operation panel is acquired, and the panel image of the operation panel is identified to obtain second operation information, the second operation information comprises second device information and a second set value; based on the matching condition between the standard operation information, the first operation information and the second operation information, the operation detection result of the target device is obtained. The present application can solve the problem of human error detection of the nuclear power plant, and timely detect the error of the human operation of the nuclear power plant.

An adjustable core assembly for a nuclear reactor is disclosed herein. The adjustable core can include a plurality of reactivity control cells configured to accommodate a reactivity control rod, and a plurality of unit cells. The plurality of unit cells defines a radial dimension corresponding to an initial power output of the core. Each unit cell of the plurality of unit cells is configured to accommodate fuel configured to generate energy and a heat pipe configured to transfer thermal energy away from the core. Each unit cell of the plurality unit cells can be coupled to an adjacent unit cell in a radial direction, thereby altering the radial dimension, wherein the altered radial dimension corresponds to an adjusted power output of the core, and wherein the adjusted power output of the core is different than the initial power output of the core.

This application discloses a design method and apparatus for the implementation scope of an intelligent operation monitoring system for nuclear power plants. The method includes: analyzing the nuclear power plant system based on its operating condition information to obtain a first system set; analyzing the first system set based on the safety function attributes, power generation function attributes, and system correlation attributes of each system in the first system set to obtain a second system set; extracting all variable parameters from the second system set to form a variable parameter library; analyzing the variable parameter library based on the screen configuration attributes of the variable parameters to obtain a DCS screen parameter set; and analyzing the DCS screen parameter set based on the type attributes and display attributes of the parameters in the DCS screen parameter set to obtain a variable parameter set for intelligent operation monitoring. This invention enables the determination of the implementation scope of intelligent operation monitoring based on objective operating data and configuration relationships, improving the technical consistency and repeatability of monitoring configuration.

This invention discloses a systematic method for reducing carbon dioxide emissions throughout the entire steelmaking and casting process, the method comprising a hydrogen injection step into a blast furnace, the hydrogen gas being supplied from a nuclear hydrogen production system, a water electrolysis hydrogen production system, and a coke oven gas-steam reforming hydrogen production system, the electricity consumed in water electrolysis hydrogen production being supplied from natural gas thermal power generation, steam residual pressure power generation, solar power generation, wind power generation, and nuclear power generation, and the combustible gas used in natural gas thermal power generation being coke oven gas, blast furnace The gas and converter gas are used. The steam used for residual steam power generation is supplied from a sintering waste heat boiler. The steam used for coke oven gas-steam reforming hydrogen production is low-pressure steam after residual steam power generation. The end products are cast steel profiles, casting materials for high-carbon spheroidal graphite cast iron profiles with a carbon content of 2-4% and a silicon content of 2-4%, and casting materials for high-carbon spheroidal graphite cast steel profiles with a carbon content of 1-2% and a silicon content of 1-1.9%. The waste from the end products is recycled and smelted in a converter or electric furnace.

The present invention relates to a method (100) and system (200) for providing efficient and sustainable heating in extraterrestrial environments is described The approach involves generating (102) substantial heat with minimal power input using a Low Energy Nuclear Reaction (LENR) core (202), which utilizes hydrogen isotopes and a metallic catalyst to produce heat through nuclear interactions without harmful radiation or hazardous byproducts. The generated heat is distributed (104) uniformly using a thermally conductive heat exchanger (204) optimized for extraterrestrial conditions, incorporating advanced insulation to minimize heat loss in vacuum conditions. An Internet of Things (IoT) enabled control system (206) monitors (106) environmental conditions and dynamically adjusts the heating output, allowing for remote control and automation. Automatic shutoff mechanisms (208) are implemented (108) to address anomalies detected by the IoT-enabled control system.

The present application relates to the intelligent test method, system and equipment of nuclear power plant radiation monitoring system, comprising: receiving the forced trigger instruction of user operation;According to the forced trigger instruction, jump from the system main interface to the forced interface;According to the trigger operation of user, select the corresponding forced control in the forced interface;According to the forced control, determine the target scheme;According to the target scheme, start one-key cancel forced operation. Through the present application, the nuclear power plant conventional island waste liquid discharge system can meet the requirements of nuclear power plant discharge standard, and can avoid the mis-triggering of nuclear power plant conventional island waste liquid discharge system during the test period, and can avoid the failure of high liquid level protection signal during normal unit operation to threaten the safety of steam turbine.

This application discloses an intelligent operation monitoring system, storage medium, and electronic equipment for nuclear power plants, including a data source module and an intelligent monitoring and early warning module. The intelligent monitoring and early warning module includes a data processing unit, an operating condition identification unit, a model building unit, and a real-time monitoring and early warning unit. The data source module is used to acquire unit operating data and unit design data. The data processing unit is used to adjust the data sampling frequency and clean the data. The operating condition identification unit is used to identify the current unit operating condition and select an intelligent algorithm and model architecture that matches the unit operating condition. The model building unit is used to construct an estimation model based on the attribute matching intelligent algorithm of variables. The real-time monitoring and early warning unit is used to monitor the deviation between the real-time measured value of the variable and the expected value of the algorithm and issue an early warning. This application can significantly reduce the workload of the main control room operator and the risk of human error, and further improve the safety, reliability, and economy of nuclear power units.

This invention relates to the field of temperature field reconstruction, specifically a method for enhancing the dimensionality of temperature reconstruction in the main pipeline of a nuclear power plant based on an ultrasonic array. It addresses the problem that existing technologies, with sparse topology structures, cannot meet the quantity and quality requirements of three-dimensional reconstruction in terms of reconstruction accuracy. The invention includes the following steps: temperature measurement and sub-temperature zone division based on an ultrasonic array; sparse dictionary training: solving for the time-of-flight (TOF) of acoustic rays in the sub-temperature zones based on physical equations; extending the measurement period; and building a neural network to enhance the dimensionality of temperature reconstruction. This invention utilizes a low-dimensional, limited number of "TOF-path" correspondences, trains a sparse dictionary, and introduces physical equations as prior information to achieve the inverse solution of nonlinear measurement equations, thereby achieving high-precision, refined reconstruction of the two-dimensional temperature field. By extending the measurement period and building a neural network, the correspondence between "A and B temperature surfaces" and the "three-dimensional pipeline" is established, thus enhancing the dimensionality of the temperature field reconstruction.

This application provides a management system and method for nuclear power plant operation processes, relating to the field of nuclear power plant operation and maintenance technology. The management system for nuclear power plant operation processes includes: a data support module storing multiple inherent state sequences corresponding to various operation scenarios, each inherent state sequence comprising multiple sequentially set inherent states; a user application module for receiving template configuration instructions; and a configuration and driving module including a process configuration unit, which generates a corresponding state flow template based on the template configuration instructions and the corresponding inherent state sequences. The state flow template includes multiple sequentially connected custom node groups, each custom node group of the state flow template corresponding to each inherent state of the corresponding inherent state sequence. The configuration and driving module stores the business rules corresponding to the inherent states, generates process instances corresponding to the state flow templates, and advances process instances according to the business rules.

The present application relates to a kind of nuclear power plant fuel assembly irradiation management method and system, its method includes: determining the operation period where unit is located;Wherein, the unit state includes normal operation period, monitoring period before overhaul, monitoring period after overhaul and abnormal period;According to the operation period where unit is located, determine data sampling strategy;According to the data sampling strategy, obtain radiochemical data;Determine the specific activity interval where the radiochemical data is located;Based on the specific activity interval where the radiochemical data is located, output operation instruction for avoiding specific activity anomaly.The present application can make fuel assembly work in suitable irradiation environment, can effectively avoid specific activity anomaly condition in primary loop, improve the safety of nuclear power plant.