31results about "Man-machine nuclear interface" patented technology

The present application relates to a kind of nuclear power plant DCS control system, including signal acquisition unit and main control room operating platform, main control room operating platform includes the control rod control system interface operating module of intermediate variable display in control rod control system;Feedwater deaerator system interface operating module for the intermediate variable display of feedwater deaerator system;Main feedwater system interface operating module for the intermediate variable display of main feedwater system;Turbine bypass discharge system interface operating module for the intermediate variable display of turbine bypass discharge system;Output link's reactor core margin calculation system operating interface link module;Chemical volume control system interface operating module for the intermediate variable display of chemical volume control system;Boron and water supply system interface operating module for the intermediate variable display of boron and water supply system.The present application can assist operator to make judgment and intervention in advance to system state by increasing intermediate variable display;More intuitively master system state, reduce human error.

A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs, each of the functionally independent modules comprising a digital module or a combination digital and analog module, an analog module electrically coupled to one or more of the functionally independent modules, and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

The application belongs to the technical field of maintenance optimization, and discloses an automatic detection device and method for a hand-operated station in a main control room of a nuclear power plant. The automatic detection device comprises a host computer, a NI virtual test instrument, a plurality of analog quantity board cards, and a plurality of to-be-detected hand-operated stations used in cooperation with the plurality of analog quantity board cards. The host computer records input voltage into the analog quantity board cards through the NI virtual test instrument. The input voltage is input into the analog quantity board cards and output from the analog quantity board cards to the to-be-detected hand-operated stations, and the to-be-detected hand-operated stations display voltage display values. The host computer collects voltage theoretical values output from the analog quantity board cards through the NI virtual test instrument. The host computer records the input voltage, the voltage display values and the voltage theoretical values, and obtains deviation values of the voltage display values and the voltage theoretical values to realize automatic detection of the to-be-detected hand-operated stations. The automatic detection device and method for the hand-operated station in the main control room of the nuclear power plant can automatically test new spare parts and aging test machines, quickly locate fault points, and provide operation and maintenance skill training functions.

A nuclear power plant virtualization system and an operation method thereof are provided. A nuclear power plant virtualization system includes: virtual machine control parts; virtual machine network parts linked to the virtual machine control parts; and a virtualization platform switch linked with the virtual machine control parts and the virtual machine network parts, wherein the virtual machine control parts include a first MMI linked driver module, the virtual machine network parts include a second MMI linked driver module, and the virtual machine control parts and the virtual machine network parts modify an IP / MAC address in data communicated with the outside and allow the data communicated with the outside from the virtual machine control parts to pass through the virtual machine network parts, via the first MMI linked driver module and the second MMI linked driver module.

A method and system for monitoring nuclear power plant axial power deviation, and a terminal device. The method for monitoring nuclear power plant axial power deviation comprises: acquiring real-time monitoring data (S10); wherein the real-time monitoring data is from a plurality of nuclear power plant monitoring systems, and the plurality of nuclear power plant monitoring systems comprise at least two of an operation monitoring system, a control rod control and position system, a nuclear sampling system and a reactor core measurement system; according to the real-time monitoring data, determining important display parameters and preset display parameters (S20); wherein the preset display parameters comprise a real-time axial power deviation, a continuous parameter, an axial power deviation influence parameter and an auxiliary function parameter; and outputting the preset display parameters and the important display parameters (S30).

The invention relates to a nuclear accident emergency exercise system based on simulation data transmission and feedback, and the system comprises a general control module which is used for receiving an external accident simulation result, constructing dose data and nuclide concentration distribution data required by simulation exercise according to the accident simulation result, and transmitting the dose data and the nuclide concentration distribution data to the general control module; the accident simulation result at least comprises radiation dose distribution and nuclide concentration; the data transmission module is used for data transmission between the master control module and the handheld monitoring module; the handheld monitoring module is used for handheld operation of exercise personnel, and can receive dose data and nuclide concentration distribution data generated by simulation data, obtain monitoring data of the surrounding environment and transmit the monitoring data back to the master control module; the monitoring data at least comprise nuclide concentration and dose varying data. According to the invention, the simulation data generated by the nuclear accident evaluation system can be transmitted to the handheld monitoring module of an on-site exercise person in real time, and is dynamically displayed on the handheld monitoring module, so that the reality sense and interactivity of the exercise are enhanced.

A nuclear power plant virtualization system and an operation method thereof are provided. The nuclear power plant virtualization system includes a virtual machine control unit, a virtual machine network unit interlocking with the virtual machine control unit, and a virtualization platform switch interlocking with the virtual machine control unit and the virtual machine network unit, the virtual machine control unit includes a first MMIS cooperation driver module, the virtual machine network unit includes a second MMIS cooperation driver module, and the virtual machine control unit and the virtual machine network unit modify IP / MAC addresses in data communicated with the outside via the first MMIS cooperation driver module and the second MMIS cooperation driver module, so that data communicated with the outside by the virtual machine control unit passes through the virtual machine network unit.

A method and system for monitoring nuclear power plant axial power deviation, and a terminal device. The method for monitoring nuclear power plant axial power deviation comprises: acquiring real-time

The invention relates to an operation mode switching method and device for a control room in a nuclear power station. Comprising the steps of determining a current operation position based on positions of a first control switch and a second control switch in real time; if the current operation position is the backup panel, the nuclear power station is controlled through the backup panel in the nuclear power station; otherwise, for any operator station, acquiring user login information of non-security level control display equipment in the operator station and position information of security level control display equipment; if the position information is the same as the login position and the operation mode is a control mode, setting a security level control display device of the operator station to be in a non-locking state; and if the position information is the same as the login position and the operation mode is not the control mode, setting a security level control display device of the operator station to be in a locked state. By adopting the method, the operation authority linkage control of the security level control display equipment and the non-security level control display equipment can be realized, and the security of the nuclear power station is ensured.

This invention provides a heating system and control method for a high-temperature gas-cooled reactor (HTGR) nuclear power plant. The HTGR heating system includes: a HTGR nuclear island, a turbine generator set, a steam generator, a primary superheater, a secondary superheater, a heating mains, a user end, a feedwater preheater, a feedwater inlet, a deaerator, a feedwater heater, a feedwater pump, and a condenser. This invention fully utilizes the main steam from the HTGR nuclear island and the extracted steam from the turbine generator set as the heating steam source for the primary and secondary superheaters of the external heating system, producing externally supplied heating steam. Based on the operating status of the HTGR nuclear island, the heating system is controlled to adopt different operating modes, thereby achieving coordinated operation of power generation and heating. This provides high flexibility, high reliability, and good safety, and helps alleviate the pressure of carbon emissions from industrial heat consumption.

A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs, each of the functionally independent modules comprising a digital module or a combination digital and analog module, an analog module electrically coupled to one or more of the functionally independent modules, and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

This application discloses systems and methods for remote control of automated equipment. The systems and methods include automated equipment configured to perform a process in a confined location by performing operations based on predetermined programming. In some embodiments, the process is a welding process and the confined location is a nuclear reactor containment building. The systems and methods also include a cellular router configured to enable communication of operating parameters between the automated equipment and a human-machine interface (HMI). An operator can use the HMI to change the operating parameters, thereby remotely modifying the operation of the automated equipment without being inside or on-site at the confined location.

To provide reactor instrumentation and control (I&C) systems capable of mitigating the effects of accidents and failures.SOLUTION: A nuclear reactor protection system includes: a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs, each of the functionally independent modules comprising a digital module or a combination digital and analog module; an analog module electrically coupled to one or more of the functionally independent modules; and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.SELECTED DRAWING: Figure 1

The application relates to a nuclear power plant fire condition accident diagnosis method, a system and a readable storage medium, the nuclear power plant fire condition accident diagnosis method comprising the following steps: after a fire occurs in a nuclear power plant, receiving fire confirmation information input by an operator; analyzing fire influence consequences of each target fire compartment respectively to obtain fire influence consequence information; determining a current affected parameter according to the fire influence consequence information and a pre-established accident diagnosis guide information database; introducing a fire confirmation signal of a target column and / or a target fire compartment into an accident diagnosis logic module related to the current affected parameter, updating the accident diagnosis logic module, and diagnosing current obtained unit state information by using the updated accident diagnosis logic module. Through the technical scheme, support can be provided for automatic diagnosis of the accident, correct execution of the accident diagnosis and the guide can be ensured under the fire condition, and the risk of human error can be avoided.

The invention belongs to the technical field of nuclear power plant reactor protection and monitoring, and aims to solve the problems of poor compatibility, insufficient expansibility, low reliability and high maintenance cost of an existing reactor protection system due to hardware customization. The invention discloses a device for a nuclear power plant reactor protection and monitoring system, which comprises a working mode management module, a power supply monitoring control module and a memory dynamic allocation and management module, and is characterized in that the working mode management module is used for switching function configuration according to a physical installation position and an application scene of the device; the working modes comprise an MTP mode and an OM working mode, the power supply monitoring control module is used for realizing full-period monitoring of a power supply state through modular design, and the memory dynamic allocation and management module is used for optimizing the memory resource use efficiency of a mainboard CPU in the OM working mode. According to the invention, monitoring, driving and testing functions are provided during unit operation, so that the reliability and safety of a reactor protection system are improved.

The present application belongs to the field of instrument control technology of nuclear power plant, and particularly relates to an intelligent information monitoring system and method. The system comprises field instruments, edge collection and processing cabinets, production control system collection and processing cabinets, central server cabinets, human-computer interaction platforms, remote intelligent VDUs, network security devices, mirror central servers and plant-level human-computer interaction devices. The output data of the field instruments are collected by the production control system collection and processing cabinets. The edge collection and processing cabinets collect intelligent business data in the field instruments. A basic platform is built for the collection, computing power and human-computer interaction resource planning, nuclear power intelligent business integration and implementation, multi-source heterogeneous data collection planning, intelligent monitoring of nuclear power operation control, operation auxiliary optimization, operation and maintenance support and management information, and operation cost reduction.

The invention discloses an automatic test system applied to the safety level SVDU function of a nuclear power plant, which belongs to the technical field of nuclear power plant test and comprises an automatic test and control unit, and a safety level DCS (Distributed Control System), a mechanical arm and a camera which are in communication connection with the automatic test and control unit. Through cooperative work of the automatic test and control unit, the safety-level DCS control system, the camera, the mechanical arm, the communication interface and other parts, comprehensive, efficient and accurate automatic test of the safety-level SVDU function of the nuclear power plant is realized, the test efficiency and accuracy are improved, manual intervention is reduced, the influence of human factors on the test result is reduced, and the safety-level SVDU function test system is suitable for the nuclear power plant. The nuclear power plant safety level system has the advantages of reducing labor cost, ensuring reliability and stability of the nuclear power plant safety level system, providing powerful guarantee for safe operation of the nuclear power plant, promoting innovative development of nuclear power plant testing technology, providing reference for automatic testing in other fields, and promoting technical progress of related industries.

This disclosure belongs to the field of nuclear power technology, specifically relating to a human-machine interface system for nuclear power plants. The system proposes a human-machine interface system for nuclear power plants. This system can establish a shared human-machine interface system for multiple nuclear power units, using video lines to output unidirectional display and control information for Safety Zone II. It can effectively allow external data to enter Safety Zone II of the nuclear power plant, and also realize real-time sharing of intelligent services between Safety Zone II and Safety Zone III. This achieves efficient and secure transmission and application of human-machine interface information for intelligent services in Safety Zone II and Safety Zone III of the nuclear power plant, while ensuring ease of use for personnel.

The invention belongs to the technical field of nuclear power, and particularly relates to a nuclear power DCS control system based on an open control technology and a construction method thereof. The invention provides a nuclear power DCS control system based on an open control technology. A simulation platform of a zero-layer simulation model is adopted to simulate physical characteristics of a nuclear power station process flow; a layer of control unit is adopted as a control system, and an open type soft PLC controller cluster (based on open type architecture construction conforming to the IEC 61131 standard) and a control cabinet are arranged; a display terminal of the system adopts a human-computer interface with an open B / S architecture. The system integrates a plurality of open source function modules and customized function modules developed for nuclear power characteristics, and realizes full coverage of a main control system and a monitoring system of the DCS of the nuclear power station.

The present invention relates to a main control room system of a nuclear power plant including a plurality of small modular reactors (SMRs) for responding to a transient state, the plurality of small modular reactors (SMRs) including a first SMR, and includes a first operator console including a first operator screen; a second operator console including a second operator screen; a supervisor console including a supervisor screen; and a control unit that, when it is determined that the first SMR is in a transient state, controls the first operator console to control the operation of only the first SMR.

This invention provides an auxiliary platform for the isolation of power circuits and loads in nuclear power plants, comprising: a standard state input module for providing users with input of the standard state of the nuclear power plant as specified in the operating technical specifications; a power supply and load object construction module for constructing objects from power sources to loads; an external information interface module for inputting the actual availability status of power supplies and switches, and the current standard state of the nuclear power plant from the nuclear power plant control system; a logic calculation module for calculating the number of unavailable devices; a simulation mapping module for providing users with the function of simulating and isolating various systems and devices in the power circuit; and a human-machine interaction module for inputting and outputting corresponding modules. This invention automatically analyzes and statistically analyzes the unavailability of nuclear power plant power circuit equipment and loads, avoiding extensive work of consulting drawings and errors caused by human negligence.

The invention relates to a device for controlling a plurality of nuclear reactors, comprising, for each nuclear reactor, a plurality of sensors for measuring operating parameters as well a system for controlling the nuclear reactor.

A component interface module with enhanced user convenience, according to the present invention, is a component interface module for managing the interface between a control system, which generates component command signals, and components, which generates component feedback signals, wherein the components are classified into first to third component groups, the component interface module is formed from first to third component interface modules, each of the first to third component interface modules includes: an input port; a processor including a priority logic, a component logic and a diagnostic logic; and an output device, the priority logic is set using a four-contact rotary switch for selecting any one of four settings in order to set the priority for the component command signals, and the component logic is set using a control rotary switch of each of the first to third component interface modules.

The present invention relates to, with respect to a main control room system, using artificial intelligence, for a nuclear power plant including a plurality of small modular nuclear reactors (SMRs), a main control room system for a nuclear power plant comprising: a first operator console which includes a first operator screen; a second operator console which includes a second operator screen; a supervisor console which includes a supervisor screen; and a control unit which self-learns data on accidents occurring in each SMR, classifies the accidents occurring in each SMR on the basis of a learning result, determines a response mode in accordance with the accident classification, and selects a console for controlling the operation of the respective SMR in accordance with the response mode.

The invention provides an artificial intelligence-based industrial safety risk identification and processing system for a nuclear power plant. The artificial intelligence-based industrial safety risk identification and processing system comprises a mobile intelligent terminal, a background command system and a closed-loop control system. And the mobile intelligent terminal is used for automatically identifying safety risks after performing scene intake on a nuclear power plant operation site, inputting identification information of the safety risks into the big data calculation model to complete evaluation and inputting an evaluation result into the background command system. The background command system is used for sending a processing instruction to the closed-loop control system according to the evaluation result. And the closed-loop control system is used for sending the processing instruction back to the mobile intelligent terminal. The safety risk in the real scene of the nuclear power plant operation site is automatically identified, analyzed and evaluated by using the big data calculation model, and a specific processing measure list is automatically given and is fed back to the mobile intelligent terminal, the background command system and the closed-loop control system in time; therefore, the probability of converting safety risks into safety accidents is effectively reduced, and safety production of a nuclear power plant operation site is ensured.

The present application provides a monitoring method and system for an accident working condition of a nuclear power plant set including the steps of : collecting accident working condition feature parameters, important unit safety signals and special safety facility states relating to typical accident working conditions (101); analyzing and processing the accident working condition feature parameters, and selecting abnormal feature parameters that are not within a preset threshold range (102); performing parallel diagnosis on the various typical accident working conditions via a number of logic calculation units (103); and displaying diagnosis results of all the typical accident working conditions on an automatic accident working condition diagnosis screen for a unit (104). According to the present application, accident working condition feature parameters, important unit safety signals and special safety facility states are monitored in real time, starting accidents or superimposed accidents of a unit are automatically diagnosed in parallel, and the accidents are displayed via a human-machine interaction interface, thereby assisting an operator in determining and handling accident working conditions of the nuclear unit.

The present invention relates to a main control room system for a nuclear power plant including a plurality of small modular nuclear reactors (SMRs), the system comprising: a first operator console which includes a first operator screen; a second operator console which includes a second operator screen; a supervisor console which includes a supervisor screen; and a control unit which classifies accidents occurring in each SMR, determines a response mode in accordance with the accident classification, and selects a console for controlling the operation of the respective SMR in accordance with the response mode.

The application relates to a replacement system of an industrial control system of a nuclear power plant, comprising a condensate water purification treatment control cabinet, a chemical reagent injection control cabinet, a feed water chemical sampling control cabinet, a data interaction module, a first virtual server and a terminal module; the data interaction module performs data interaction between the chemical reagent injection control cabinet, the feed water chemical sampling control cabinet and the first virtual server; the first virtual server replaces the industrial computer function of the condensate water purification treatment system, the chemical reagent injection system and the feed water chemical sampling system; the terminal module issues control instructions and / or control parameters to the first virtual server and outputs and displays the running data and state data of each system. The first virtual server replaces the industrial computer function of the original system, and the first virtual server executes the functions executed by the industrial computers of each system, so that the problems of unstable running, slow running, system crash and the like of the industrial computer and the influence of the problems on the normal monitoring of the system running state are avoided.

The systems and methods generally include a nuclear power plant unit assembled in a shipyard from a plurality of structural modules, each of the structural modules having manufactured components for use in power production when moored or fixed to a floor at least one of in and proximal to at least one of an offshore marine environment, a river environment and a coastal marine environment. The nuclear power plant unit is subdivided into at least one arrangement of structural modules that includes an electrical interface for one of transmitting electrical power generated by the nuclear unit and powering a system of the unit, a communications interface for communications internal or external to the unit, a user interface that is configured to permit a user to access a system of the unit, and a network interface for data communications to or from the unit.