63results about "Man-machine nuclear interface" patented technology

The invention discloses a safety display and control integrated system of a nuclear power station, which relates to the field of safety level control of the nuclear power station and comprises an FPGA module, an MCU module and a CPLD module. The FPGA module is connected with the MCU module; the FPGA module and the MCU module are both connected with the CPLD module; the FPGA module is used for collecting and transmitting ring network data; the MCU module is used for display control and communication processing; the CPLD module is used for diagnosing the running state of the FPGA module and the running state of the MCU module; the MCU module comprises a display core and a communication core; the display core is used for running a GUI graphic function; the communication core is used for operating communication, control and recording functions. The safety display unit which is safe, stable and reliable in operation is provided for a nuclear power station safety level control system.

Systems and methods provide data gathering and execution on the same without human operations. Systems may include controls and sensors that electronically provide data and operations to a processor networked with the same. For a nuclear reactor, the processor may determine reactivity from the sensors and issue commands to actuators to operate the reactor. Reactivity may be determined based on all reactivity 10 factors determined from the plant data, including the use of modelling. The processor may position control elements or moderator feeds to achieve a desired reactivity. The processor may be networked to plant switches and sensors, and multiple processors may be used to independently calculate and decide on plant operations. Human operator input is not required at discreet instances of plant operational change; systems 15 may include displays and input interfaces to permit observation and / or intervention if absolutely necessary.

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.

The invention belongs to the technical field of nuclear power station instrument control, and particularly relates to a diversified protection system and method for improving the safety of a power station. Comprising the following steps: a processing method when a primary loop crevasse occurs and a common cause fault occurs in the RTS-ESFAS, a processing method when a secondary loop crevasse occurs outside a containment and the common cause fault occurs in the RTS-ESFAS, and a processing method when a secondary loop crevasse occurs in the containment and the common cause fault occurs in the RTS-ESFAS. The diversified protection system has the beneficial effects that under the condition that RTS shutdown protection fails, the control rod driving mechanism power-off command is generated again in a manner of changing a triggering fixed value, and the control rod driving mechanism power-off command acts on a circuit breaker different from an RTS system, so that reliable shutdown of a reactor is realized.

The present invention discloses a method and system for inspecting a nuclear power plant pool. The method includes: S1, generating a vertical inspection task list and / or a horizontal inspection task list according to inspection data; S2, formulating an inspection path for each inspection task according to the three-dimensional data of the pool and each inspection task list; S3, generating position data according to the inspection path of each inspection task; S4, controlling an inspection device to execute each inspection task according to the inspection path and the position data; S5, issuing a monitoring result according to the detection data of each inspection task. By using the inspection device to replace the traditional manual visual inspection, the present invention can perform a close-range line-of-sight inspection on the inspection objects in the water-filled pool and the empty pool, reducing the radiation safety injury risk of personnel operations and effectively improving the efficiency and inspection effect of the pool inspection operation.

Systems and methods provide data gathering and execution on the same without human operations. Systems may include controls and sensors that electronically provide data and operations to a processor networked with the same. For a nuclear reactor, the processor may determine reactivity from the sensors and issue commands to actuators to operate the reactor. Reactivity may be determined based on all reactivity factors determined from the plant data, including the use of modelling. The processor may position control elements or moderator feeds to achieve a desired reactivity. The processor may be networked to plant switches and sensors, and multiple processors may be used to independently calculate and decide on plant operations. Human operator input is not required at discreet instances of plant operational change; systems may include displays and input interfaces to permit observation and / or intervention if absolutely necessary.

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.

The present invention relates to the technical field of nuclear power plant equipment monitoring, and discloses a method and system for monitoring the action of switch quantity equipment in a nuclear power plant. The method compares the action changes of all equipment within a time period, records the number of changes and the specific time of the changes, and directly assigns the traversed data to the temporary variable if the temporary variable is empty. If the temporary variable is not empty, it is determined whether the value of the temporary variable is the same as the variable value. If the value of the temporary variable is the same as the variable value, the next value is traversed. If the values ​​are different, it is determined that the data has changed, the change is input into the result of the data comparison module, and the current data is assigned to the temporary variable, and the next data is traversed. The system includes an automatic display module, a query display module, a data comparison module and a drawing association module, and the data comparison module is used to determine whether the temporary variable is empty. The present invention enables the main control operator to grasp the action of all equipment of the nuclear power unit under his jurisdiction in real time and efficiently.

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.

The invention relates to an operation system for automatic action confirmation of a steam turbine under the accident condition of a nuclear power plant, and the system comprises an information obtaining module which is used for obtaining the state or parameter of nuclear power equipment related to each automatic action confirmation regulation in real time; the information display module is provided with a plurality of automatic action confirmation areas, and each automatic action confirmation area is used for displaying the state or parameter of the nuclear power equipment related to the corresponding automatic action confirmation regulation; and the control module is used for controlling the corresponding nuclear power equipment according to the operation instruction input by the user. The states or parameters of the nuclear power equipment related to all the automatic action confirmation regulations are concentrated together to be displayed, so that an operator can conveniently check, operate and control the nuclear power equipment according to the automatic action confirmation regulations, the execution efficiency of accident regulations is improved, the failure risk is reduced, and a steam turbine is better protected.

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.

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 discloses a method and system for reusing a nuclear power plant monitoring system. The method includes: obtaining the operating status of the unit through the life monitoring unit of the main monitoring system, where the operating status is determined by the non-safety level and safety level states of the main monitoring system, as well as the non-safety level and safety level states of the auxiliary monitoring system. The auxiliary monitoring system switches modes with the main monitoring system through a multi-channel switching system, and the auxiliary monitoring system reuses the display terminal of the main monitoring system. Based on the operating status, the monitoring status of the auxiliary monitoring system, a diversified human-machine interface panel, or an extended operating condition and emergency panel is activated through the multi-channel switching system. This method can simplify the human-machine interface equipment in the control room, reduce project costs, and complete the monitoring and control of normal and emergency conditions of the nuclear power plant, thereby effectively ensuring the safety and operation of the nuclear power plant.

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.

The present invention provides a failure downgrade operation method and system for a nuclear power plant control room. The method includes: using a KIC system to construct a pre-defense line in a control room defense in depth system (S11); using an ACP and an ECP to construct a main defense line in the control room defense in depth system (S12); using a DHP panel to construct a diversity defense line in the control room defense in depth system (S13); and using an SAP panel to construct a serious accident mitigation line in the control room defense in depth system (S14). Positioning of a device belonging to a serious accident defense line in a failure downgrade operation strategy is considered, the problem of the mixed arrangement of devices at different defense in depth levels and in different failure running modes is solved, the failure downgrade operation strategy of the control room is clear, and the related dedicated devices are configured to significantly reduce the difficulty that an operator handles failures of HSIs, reduce the human error probability, and improve the safety of a nuclear power plant.

The present invention relates to the field of nuclear safety and nuclear emergency technology, and specifically to a nuclear power plant tracking and prediction system control middleware implementation system and method. In order to ensure the scientific nature of the nuclear emergency decision-making process, it is necessary to develop nuclear power plant tracking and prediction software to support scientific analysis of the occurrence and development process of accidents, and provide feasible accident mitigation measures to minimize the harm of accidents to the public. The nuclear power plant tracking and prediction system consists of two state tracking calculation modules, four identical prediction modules and a control middleware based on a real-time memory database. The implementation method includes selecting an operating mode; the tracking module performs tracking calculations; starting the prediction module; the prediction module performs prediction calculations; and user intervention. The present invention is a nuclear power plant tracking and prediction software that can be used to provide technical support and guidance for nuclear emergency decision-making and accident disposal.

The present invention provides a computerized procedure method and device for a high-temperature gas-cooled reactor power plant. The method obtains real-time operation data of the high-temperature gas-cooled reactor power plant and determines whether the real-time operation data of the power plant meets the procedure entry conditions; performs procedure processing on the real-time operation data of the power plant that meets the procedure entry conditions to obtain a procedure processing result; and transmits the procedure processing result to the corresponding position of the high-temperature gas-cooled reactor power plant so that the high-temperature gas-cooled reactor power plant correspondingly executes the procedure processing result. Through the present invention, procedure information is displayed to the operator in a graphical or text-based manner on the operator interface, helping the operating personnel to more effectively use the procedures to control the nuclear power plant. The computerized procedures can assist in the use and management of the operating procedures and play a better supporting role for the operator during normal or emergency operations.

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.

The present invention relates to a design method for an automatic start-stop and intelligent monitoring system for a nuclear power plant, which belongs to the technical field of nuclear power plant automation control, and includes the following steps: task analysis of the start-stop operation process of a nuclear power plant; determining the design scope of an ANPS system of a nuclear power plant; functional group design of an ANPS control system of a nuclear power plant; design of a sequence control function flow of an ANPS of a nuclear power plant; design of a closed-loop adjustment function of main process parameters of an ANPS system of a nuclear power plant; design of an intelligent monitoring module for the operation status of a unit start-stop process of an ANPS system of a nuclear power plant; integrated design of an ANPS system of a nuclear power plant; design of a human-machine interface function of an ANPS system of a nuclear power plant; verification and confirmation of a design scheme of an ANPS system of a nuclear power plant. The method provided by the present invention can realize automatic start-stop sequence control, closed-loop adjustment of main process parameters, and intelligent monitoring of unit operation status parameters in a full operating range of a nuclear power plant.

The invention relates to the technical field of object transfer, in particular to an object transfer device and method for a master control room of a nuclear power plant, and the device comprises a protection module which is installed on a wall body of the master control room; the transmission module is arranged in the protection module and is used for loading an object to be transmitted; the ventilation module is connected with the protection module and used for keeping air circulation inside and outside the protection module and maintaining air pressure balance; the purification module is located at the position, close to the outer side of the main control chamber, of the protection module and used for purifying air entering or leaving the protection module; and the article box is placed in the transmission module. The main control room has the beneficial effects that the object transferring device is arranged on the wall body of the main control room, and an object transferring way is provided for the main control room. Files and articles in and out of the master control room are transmitted through the article transmission device, and the articles can be transmitted without opening the door of the master control room. The frequency of personnel entering and exiting the master control room is reduced, and the influence of the outside on the personnel in the master control room is reduced.

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

A method for determining a default value of signal of nuclear power plant control system, and a terminal equipment. The method comprises: acquiring at least one preset default value of a target signal, and failure-association data capable of representing an action correspondingly executed by a control system after the target signal fails (S10); performing impact analysis on each preset default value according to the failure-association data to obtain a detection difficulty score, an impact severity score and a redundancy degree score (S20); determining a total score corresponding to each preset default value according to the detection difficultly score. The impact severity score and the redundancy degree score corresponding to each preset default value, and determining a configurable default value of the target signal according to all the total scores and (S30). The value-taking analysis method and the terminal equipment can help a worker to rationally evaluate the rationality of each preset default value of a control signal. And recommend the most rational preset default value to the worker as a recommended value of default value.

Disclosed herein is a nuclear instrumentation and control system. The nuclear instrumentation and control system may include a housing and a plurality of selectively removable completed board assemblies installed within the housing and configured to be electrically connected to a nuclear reactor of the instrumentation and control system. At least one of the selectively removable completed board assemblies includes input / output circuitry. The nuclear instrumentation and control system may further include a daughter card including control circuitry, the daughter card configured to be selectively connected to at least one selectively removable base board of the plurality of selectively removable base boards via a mechanical connector and an electrical connector.