153results about "Man-machine nuclear interface" patented technology

A reactor control interface includes a home screen video display unit (VDU) displaying blocks representing functional components of a nuclear power plant and connecting arrows that connect blocks that are providing the current heat sinking path for the nuclear power plant. Directions of the connecting arrows represent the direction of heat flow along the current heat sinking path. If the current heat flow path of the plant changes, the connecting arrows are updated accordingly. Additional VDUs include: a mimic VDU displaying a mimic of a plant component; a procedures VDU displaying a stored procedure executable by the plant; a multi-trend VDU trending various plant data; and an alarms VDU displaying side-by-side alarms registries sorted by time and priority respectively. If a VDU fails, the displays are shifted to free up one VDU to present the display of the failed VDU, and one display is shifted to an additional VDU.

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.

A monitoring and operation image integrating system include: a display signal synthesizing unit to which a display signal from a plurality of safety equipments and that from non-safety equipment are inputted, and which synthesizes a display signal from the plural safety equipments and a display signal from the non-safety equipment; display signal switching unit to which a state signal showing an operation state of whether or not each monitoring and operation screen image of the plural safety equipments displays an operating device of the equipment, is inputted, and which switches a display signal from a safety equipment to be synthesized by the display signal synthesizing unit based on the inputted state signals; and an integrated monitoring and operation screen display that displays a display signal synthesized by the display signal synthesizing unit as an integrated monitoring and operation screen of a plant.

An integrated monitoring method and a system using the same which can monitor structural integrity or an operating state of a nuclear device are provided. One integrated analysis unit receives a plurality of signals in order to integrate, mutually exchange, and analyze from a plurality of heterogeneous sensors installed in the nuclear device. The integrated analysis unit may notify an operator with an alarm since an alarm unit may be adhered to the integrated analysis unit. Accordingly, the present invention may provide accurate, useful, and various information due to integration of the sensor signal while not increasing a number of installed sensors, manufacture a simulator by generating a database of the sensor signals, or use a past signal as data for an optimum design by researching and analyzing the past signal.

The invention discloses a control method of a nuclear power station safety level DCS. The control method includes the steps that two or more driving signals sent by equipment are received; the driving signals are subjected to priority ranking according to preset priority management logic; a first driving instruction is generated according to the ranked first driving signal so that an equipment driving device can execute operation according to the first driving instruction. According to the control method of the nuclear power station safety level DCS, in the control process of a nuclear power station safety level digital instrument control system, a multifunctional and intelligent control technology can be achieved. Besides, the invention discloses a multifunctional interface of the nuclear power station safety level DCS.

A nuclear instrumentation and control system, comprising: an input module, receiving analog inputs from sensors and digital signals from hardware switches; a dual redundant bi-stable processor, connecting to the input module; a dual redundant local coincidence logic processor, connecting to the dual redundant b0-stable processor; an output module, connecting to the dual redundant local coincidence logic processor; an integrated communication processor, connecting to the dual redundant bi-stable processor and the dual redundant local coincidence logic processor; an interface and test panel, connecting to the dual redundant bi-stable processor, the dual redundant local coincidence logic processor and the integrated communication processor; and a video display unit, connecting to the dual redundant bi-stable processor, the dual redundant local coincidence logic processor, the integrated communication processor and the interface and test panel. Thereby, a qualification and certification tools for design and development of safety related equipment and explains the basis for many decisions made while performing the digital upgrade.

The invention discloses an intelligent accident handling rule operating method of a nuclear power plant. The method comprises that bottom layer information related to the running state of the nuclear power plant is calculated intelligently according to functions or purposes, and multiple decision types of information related to the SOP rule operation sheet and execution path are obtained; whether the running state of the nuclear power plant satisfies the corresponding decision type information is determined; the SOP rule operation sheet as well as operation device icons and decision type information corresponding to the SOP rule operation sheet are displayed in the same display interface; and according to comparison and calculation of the SOP rule operation sheet, the running state of the nuclear power plant and the decision type information, corresponding operation is executed automatically, and accidents are handled. According to the invention, information is integrated and displayed dynamically, frequency calling of the display frame is not needed, and the execution efficiency is improved; dynamic lines and intelligent diagnosis information can prevent an operator from misjudgment, and the execution accuracy is improved; and in addition, automatic diagnosis of the rule is realized by an automatic sequence execution function, and the workload of operators is reduced.

The invention relates to the technical field of accident monitoring of mega-kilowatt nuclear power plants, and provides a method and a system for monitoring the operating state of a nuclear power plant and a storage medium. The method comprises the following steps: acquiring information on the operating state of the nuclear power plant, wherein the information on the operating state of the nuclearpower plant comprises information on reactor characteristic parameters, information on the operating state of an energy supply system, information on the operating state of a nuclear steam supply system, and parameter information during operation of equipment and the system; respectively displaying the information on the operating state of the nuclear power plant on different display interfaces according to preset classification. Through the method and the system for monitoring the operating state of the nuclear power plant and the storage medium, the operating state of the nuclear power plant can be effectively and intuitively displayed on the display interfaces, so that monitoring personnel can effectively and intuitively monitor the operating state of the nuclear power plant.

The invention discloses a serious accident instrument control system for a nuclear power station, comprising an on-site instrument layer, a logic processing layer and an operation and information management system; the on-site instrument layer comprises an on-site instrument and an on-site executing mechanism; the on-site instrument and the on-site executing mechanism can be used for executing functions under serious accident, design basis accident and normal running condition; the logic processing layer collects the information from the on-site instrument layer, and outputs information to the operation and information management system to display; the operation and information management system receives and sends the control order to the logic processing layer, and the logic processing layer outputs the control order to the on-site instrument layer to execute. The serious accident instrument control system for the nuclear power station is supplied by regular power source and specific UPS at the same time. Compared with the prior art, the serious accident instrument control system for the nuclear power station guarantees that the serious accident handling strategy is effectively practiced under the condition of serious accident and lost alternating current of the whole plant, and the safety of the nuclear power station is improved.

The invention discloses a method and a system for detecting man-machine interfaces. The method for detecting the man-machine interfaces includes steps of identifying risk scenes where the no-response probability of actions exceeds a preset threshold value on the basis of an HCR (human cognitive reliability) process; determining error probabilities of various tasks or the various actions in the identified risk scenes by a CREAM (cognitive reliability and error analysis method); and sequentially checking the man-machine interfaces involved in the various tasks or the various actions with a preset human engineering checklist according to magnitudes of the error probabilities to determine defective man-machine interface units. The method and the system have the advantages that the digital man-machine interfaces of a nuclear power plant are evaluated by the HCR, CREAM and HEC (human engineering checklist) combined method, and the defective man-machine interface units in the digital man-machine interfaces are quickly and efficiently detected, so that deep-seated design defects which cause human errors can be found, and the running safety of a digital control system of the nuclear power plant is integrally improved.

Provide an operation management support apparatus for power plant, supporting a maintenance work and preventing a user from violation of the operational safety programs, caused by a human error in case where a power plant temporarily deviates from LCO. The operation management support apparatus for power plant includes: an alarm device 12 that compares a plant data measuring by sensors 3a-3x installed in a nuclear power plant 2 with preset alarm the value and generates an alarm output instruction signal for instructing an alarm output in case of determining that the power plant is abnormal; an operational safety program DB 14 that stores an information in relation to an operational safety program of the power plant; an support device 13 that extracts an information in relation to the operational safety program of which the alarm output represents a conflict from the operational safety program DB 14 based on the plant data in relation to the alarm output in case of receiving the alarm output instruction signal; and a display device 15 (16) that displays the plant data and the information in relation to the operational safety program, extracted by the support deice.

The embodiment of the invention provides a nuclear power plant priority management system comprising a priority management device connected with a hard-wired interface and a security-level instruction interface. The priority management device is also connected with a non-security-level communication interface through the hard-wired interface; and the non-security-level communication interface is used for realizing connection with a non-security-level system and receiving a non-security-level equipment-level control instruction from the non-security-level system. The nuclear power plant priority management system is integrated with the hard-wired interface, the security-level instruction interface, and the non-security-level communication interface and thus can receive control instructions all security-level systems conveniently, so that the engineering applicability is high. Moreover, on the basis of direct connection of the non-security-level communication interface with the non-security-level system, connection of lots of hard wiring can be avoided, so that usability of the system in terms of project implementation can be improved.

The invention discloses a nuclear power station main control and auxiliary control switching method comprising the steps that a starting command is sent to an auxiliary control system by a switching switch; whether the auxiliary control system performs activation operation according to the starting command is judged by a logic processing unit; if the auxiliary control system performs activation operation according to the starting command, a shutting command is sent to a main control system by the switching switch; and the main control system performs stop operation according to the shutting command. The main control system for nuclear power station operation control is switched to the auxiliary control system so that a situation that nuclear power station operation cannot be controlled under the emergency situation that a main control chamber including the nuclear power station main control system loses control can be avoided. Besides, the invention also discloses a nuclear power station main control and auxiliary control switching system.

The invention discloses a nuclear power station reactor protection system safety parameter monitoring device and a nuclear power station reactor protection system safety parameter monitoring method. The device comprises a safety parameter transceiver module, a safety parameter processing module and an authority setting module, wherein the safety parameter processing module comprises a storage module, a verification module and a modification module. The method comprises acquiring an actual safety parameter, processing the actual safety parameter and setting a display interface. The device and the method are based on a digital reactor protection system and can calibrate a real-time safety parameter, and furthermore can transmit the calibrated parameter to a corresponding CPU unit for operation. Furthermore the display interface is utilized for visually displaying data and understanding the data, thereby performing quick and accurate processing on the parameter, and preventing errors in setting and modification. A parameter modification log is formed, and a parameter modification process can be traced in a log file. Furthermore batch parameter modification can be performed, thereby saving labor and improving operation efficiency.

The invention discloses a method and a device for gang controlling the screen of master control room of nuclear electrical power plant. The method comprises the following steps: receiving switching request of the first screen of the linkage screen group, making the display frame specified by the switching request be the main control screen. Making the first screen as the master-control panel. In addition, the screens except the first screen are used as linkage screen. The linkage screen group comprises a plurality of screens, each screen is used to display different pictures when the current task is executed, and switch the main control screen frame to the main control screen. At least one linkage screen is controlled to switch to the linkage picture corresponding to the master control screen. Compared with the prior art, In the process of operation, when the operator change the display content of a screen, the other screen which is related to the screen is changed. At the same time, the operation efficiency is improved, the operator workload is reduced, and the risk of human error caused by the operator invoking display screen is reduced.

The invention discloses a method and a system for demonstrating a nuclear accident status change in a nuclear power plant. The method comprises steps: data needed for accident monitoring are acquired; the data are converted to data with time serialization characteristics and are stored to an emergency database; an accident sequence change diagram is stored to the emergency database; data in the emergency database are extracted, the data are analyzed and judged according to the existing rule, and the status of each accident node in the current accident sequence change diagram is obtained; and the current accident sequence change diagram is displayed, and the calculated status of each accident node is displayed on the accident sequence change diagram. The system comprises a data acquisition module, an emergency data recording module, an emergency database, a core processing module, a display module and the like. Based on real-time data, an accident sequence in a nuclear emergency status can be logically organized, the change can be demonstrated dynamically, and a visual technical support is further provided for an emergency post person and a decision-making person.

An Instrumentation and Control (I&C) system for Emergency Diesel Generator (EDG) of the nuclear power plants is provided. The instrumentation and control system is adapted to be divided into two parts: first and second control parts. The first control part includes Safety I&C functions adapted to be controlled by wired logics based on electromechanical relays. Further, the second control part includes Non-safety I&C functions adapted to be controlled by Programmable Logic Controllers (PLCs)/Human Machine Interface (HMI).

The invention provides a nuclear power plant control room comprehensive information display system and method. The system comprises a display module and a nuclear power plant monitoring module connected with the display module, the display module comprises multiple display sub-modules, and the display sub-modules display nuclear power plant information in the same area, the nuclear power plant monitoring module is used for controlling each display sub-module to display the corresponding nuclear power plant information when a nuclear power plant runs normally; under the nuclear power plant accident working condition, one of the display sub-module is controlled to perform sound and light alarm, and another display sub-module is controlled to display alarm information synchronously. Accordingly, all nuclear power plant safety parameter display system parameters of the nuclear power plant are easily, rapidly, reliably, continuously and fixedly displayed, an operator can monitor and rapidlyknow the state of the nuclear power plant conveniently, and information processing and nuclear power plant control are efficiently conducted.

The invention discloses a reactor protection system channel response time intelligent testing system and method. The system comprises an integrated controller, a first channel selector, a second channel selector, and a high speed record card. The integrated controller is used for outputting a group simulation signal and a channel selection control signal and is connected with a nuclear power plant digital control system. The first channel selector is used for receiving the group simulation signal and selecting one signal as a protection input record sample according to the channel selection control signal. The second channel selector is used for receiving the channel selection control signal and selecting one signal as a protection output record sample according to the channel selection control signal. The high speed record card is used for recording change time difference data of the protection input record sample and the protection output record sample. The integrated controller carries out calculation according to the change time difference data to obtain reactor protection system channel response time, so that automation of the whole testing process and automation of data processing can be achieved, and lots of time and cable consumables are saved.

The invention discloses a transmission station for a security level instrument control system of a nuclear power plant. The transmission station is positioned among information transmission links of the security level instrument control system, and the security level instrument control system comprises an onsite control station, a security display station, an emergency control panel/backup panel, an engineer station and a gateway station. The transmission station is simultaneously connected with the onsite control station, the security display station, the emergency control panel/backup panel, the engineer station and the gateway station. The transmission station is used for executing collection and processing of fault diagnosis information of the security level instrument control system and further used for executing information exchange with the onsite control station and information exchange with the engineer station.

The invention provides a remote shutdown station system and method for a nuclear power plant. The remote shutdown station system comprises a remote shutdown station, an operator workstation module arranged in the remote shutdown station, and a switching unit assembly arranged inside and outside the remote shutdown station; the operator workstation module is used for receiving and processing monitoring information identical to a main control room when the main control room is unavailable; the switching unit assembly is connected with a logic control cabinet and is used for sending a switching instruction according to different states of the nuclear power plant; the logic control cabinet is in communication connection with the main control room and the operator workstation module and is usedfor receiving the switching instruction, performing logical processing on the switching instruction, and then switching to the main control room or the operator workstation module to receive and process monitoring information in a distributed control system (DCS) monitoring network of the nuclear power plant. The invention solves the problem that a part of process system logic is forced to be automatic when being switched to a remote shutdown station system due to limited monitoring means, and the monitoring range of the monitoring function is enlarged.

The invention provides a nuclear power plant-based SOE data acquisition method. According to the nuclear power plant-based SOE data acquisition method, signal acquisition devices which are in one-to-one correspondence with nuclear power plant filed apparatuses, and an SOE processor are provided, wherein the SOE processor is a single-chip microcomputer. The nuclear power plant-based SOE data acquisition method includes the following steps that: the signal acquisition devices acquire the states of the nuclear power plant filed switching apparatuses real time, and transmit the acquired states to the SOE processor; and the SOE processor performs processing according to the states of the switching apparatuses and change situations of the states, so that the operation situations of a current switching apparatus can be obtained, wherein the operation situations are divided into events, interferences or stable states, if the operation situation of the current apparatus is an event, the SOE processor reports the event to a control station. With the nuclear power plant-based SOE data acquisition method adopted, whether a situation is a real event or jitter can be distinguished.

The invention belongs to the technical field of nuclear safety control and relates to a remote shut-down amplifier station operation and control method when a main control chamber of a pressurized water reactor nuclear power plant is in a forbidden state. The operation and control method includes steps of (1), an operators goes to a remote shut-down amplifier station for operation and control andperforms manual shut-down when the pressurized water reactor nuclear power plant is in the forbidden state; (2), a natural circulation method is adopted in remote shut-down amplifier station operationand control for temperature lowering and voltage reducing when a main pump cannot run; (3) a forced circulation method is adopted in shut-down amplifier station operation and control for temperaturelowering and voltage reducing when the main pump can still run. By adopting the operation and control method provided by the invention, different handling measures can be taken according to that whether the main pump can run or not and the mode of a machine unit through fully utilizing advantages of the digital nuclear power plant and combining with characteristics of the full function remote shut-down amplifier station when the main control chamber of the pressurized water reactor nuclear power plant is in the forbidden state and the operators goes to a remote shut-down amplifier station foroperation and control.

The invention discloses a nuclear power station rotating machine driving control method which comprises the steps that obtained signals are subjected to logic processing, and device-level control instructions are formed; the control instructions are converted to specific instruction signals which can be identified by rotating machine equipment, and feedback signals of the rotating machine equipment according to the specific instruction signals are received; according to the feedback signals, whether a fault happens to the rotating machine equipment is judged; and if yes, the rotating machine equipment is subjected to reset control. The nuclear power station rotating machine driving control method is a reliable nuclear power station rotating machine driving control technology, and safe operation of the rotating machine equipment under various working conditions can be guaranteed. In addition, the invention discloses nuclear power station rotating machine driving control device.