177results about "Nuclear power plant control" patented technology

The invention relates to a device and a system for monitoring and displaying normal operating condition of a unit of a nuclear power plant. The nuclear power generating unit has a plurality of operating modes; on a display device, a monitoring module is imported aiming at one operating mode; the monitoring module comprises four units displaying simultaneously, namely a trend tracking unit, a value display unit, a device state unit and an accident condition indication unit. The technical scheme of the invention is that: a reactor operating mode is dominant so as to perform a system monitoring design; according to the change of the normal operating state of the nuclear power generating unit, for a certain working mode, frequent and intersystem monitoring and analysis are needed; parameters and equipment to be monitored are concentrated in a unified monitoring module and displayed through the display device so as to facilitate the monitoring and operation of the total state of the nuclear power generating unit; and the defect of a DCS (digital control system) in the aspect of intuition is overcome, the advantages of a control room of the DCS are fully played, and the safe and stable operation of the nuclear power plant is ensured.

The invention is applicable to the field of nuclear power control, and provides a method and a system for digitalizing an overall grogram of a nuclear power plant and a digital control system (DCS) control system. The method comprises the following steps of: searching a digitalized operation sheet corresponding to task information according to a program main body, wherein the program main body comprises output task information, digitalized operation sheet information corresponding to the task information and supporting interface information; outputting task detail information, equipment information corresponding to the task detail information, and link information according to the searched digitalized operation sheet; and sending a link instruction to the supporting sheet by the digitalized operation sheet, and outputting a monitoring parameter and an operation instruction across the system by the supporting interface which receives the link instruction. By the invention, the defect of the DCS in the intuitive aspect is overcome, the operating efficiency of the overall program of the nuclear power plant is improved, and the advantages of the DCS in information processing are fullyexerted.

The invention discloses a simulation device and simulation method of an on-site driving apparatus of a nuclear power station. Simulation of the on-site driving apparatus of the nuclear power station is realized in a function test of a DCS (Digital Control System) of the nuclear power station. The simulation device of the on-site driving apparatus of the nuclear power station comprises a simulator and an interface cable; and the simulator is seamlessly terminated with the digital control system through the interface cable. The simulator comprises at least a channel circuit; and each channel circuit enables the simulator to respectively simulate corresponding apparatuses by switching states of interconnected first switching component and second switching component so as to make a corresponding response to a command signal sent from the digital control system, so that a user has no need to build a model and organize states in the function test of the DCS control system of the nuclear power station. However, a plurality of independent channel circuits enables the simulation device of the on-site driving apparatus of the nuclear power station disclosed by the invention to have high operational reliability and discover and remove fault points conveniently.

The invention discloses a multifunctional driving module, and relates to the field of nuclear power plants. The multifunctional driving module comprises an input interface and an output interface; a testing circuit module, a functional logic circuit module and an output voting circuit module are arranged in the driving module; and the input interface comprises a control signal input interface anda testing signal input interface. The driving module employs programmable hardware (such as a CPLD (Complex Programmable Logic Device) or an FPGA (Field Programmable Gate Array) chip) to design the functional logic circuit, and the internal logic can be compiled according to the practical use, for example, the redundant voting (such as AND or NOT) logic and the priority processing logic for a received control signal are realized. The driving module is designed by a hardware circuit without operating software, and is high in reliability; and all the interfaces are in the form of hard wiring and can undergo interface application with automatic control platforms such as DCS (Distributed Control System), PLC (Programmable logic controller), etc.

The invention discloses a method and system for verifying the default value of a digital instrument control system signal of a nuclear power plant, wherein the method includes the following steps: receiving the signal of the digital instrument control system; judging whether the signal of the digital instrument control system is valid; The signal of the control system is replaced by the preset default value; the default value of the digital instrument control system signal is verified; the relevant data in the verification process is recorded. The invention verifies the default value of the signal of the digital instrument control system of the nuclear power plant, and records the relevant data in the simulation verification process, so as to analyze the verification situation of the default value according to the records, continuously improve the setting of the default value, and improve the safety of the nuclear power plant and usability.

The invention relates to a digital control system (DCS) signal ineffectiveness processing method and a digital control system (DCS) signal ineffectiveness processing system for a nuclear power station. The method comprises an ineffectiveness detecting step, namely detecting whether an input DCS signal is effective, if so, outputting the DCS signal to a downstream processing device to realize DCS logic control, and otherwise, executing a data processing step; and a data processing step, namely calling a DCS default value corresponding to the ineffective DCS signal from a default value databaseto replace a signal value of the ineffective DCS signal, and outputting the processed DCS signal to the downstream device. By performing ineffectiveness process on the DCS signal, the DCS default value can immediately substitute for the DCS signal when the DCS signal becomes ineffective; therefore, the function of the DCS is optimized, the control system of the nuclear power station can be kept running safely and stably, and the casualty chance of people and the damage chance of devices are reduced.

The invention relates to a simulation adjustment method of digitized control configuration for a nuclear power plant, comprising the following steps of: establishing a minimum structure of digital control system; establishing a connection of a simulation system and the minimum structure of digital control system; establishing a simulation tracking configuration logic of the digitized control configuration of the nuclear power plant on the minimum structure of digital control system, getting the dynamic operation data of the digitized control configuration of the nuclear power plant on the minimum structure of digital control system through the simulation system; and storing the dynamic operation data. The invention further relates to a simulation adjustment system of digitized control configuration for the nuclear power plant, comprising the minimum structure of digital control system, and the simulation system connected with the minimum structure of digital control system. The invention solves the problem of simulation adjustment of digitized control configuration for the nuclear power plant, which promotes the adjustment progress of nuclear power plant project as well as provides reliable quality assurance of the digitized control configuration for the nuclear power plant.

The embodiments of the invention disclose a nuclear power station digitization distributed control system and an isolation method thereof. The system comprises a safety grade subsystem and a non-safety grade subsystem and is characterized by further comprising multiple safety grade AC power buses. Devices in the safety grade subsystem are respectively energized by the independent safety grade AC power buses so as to maintain mutual independence among the devices in the safety grade subsystem; and the non- safety grade subsystem is also energized by the independent safety grade AC power buses, and electrical isolation devices are arranged between the safety grade AC power buses and the non-safety grade subsystem so as to maintain mutual independence among the safety grade AC power buses and the non-safety grade subsystem. By implementing the system and the method provided by the invention, the safety of the nuclear power station digitization distributed control system can be improved.

The invention relates to a playback method of production process for a nuclear power plant and a system. The method comprises the steps of: collecting the real time data of the production process of the nuclear power plant, filtering, compressing and storing the real time data collected; receiving a playback request, starting the client, connecting and loading the historical database information, and loading the homepage; getting the historical data of page in the period for request; synchronizing the historical data obtained and the request page; and displaying the page synchronized with the data to the users. The invention further relates to a playback system of the production process for the nuclear power plant, comprising a data collecting unit, a data processing and storing unit, a playback controlling panel, a starting and loading unit, clients, a request processing unit, a synchronization processing unit and a cache unit. The invention achieves the random call of page playback in any period and can analyzing the faults accurately and quickly, which increases the safety factor of safe operation of the unit, reduces the labor cost and time cost for the analysis and process of faults.

The invention discloses a nuclear power plant DCS function verification method which includes: clicking a nuclear power plant instrument control topology graph on a testing interface to select the cabinet which the to-be-verified DCS belongs to; clicking the movable parts in the DCS to generate fault insertion list information; driving a virtual DCS simulation verification platform to perform verification according to the fault insertion lift information. By the method, efficient and fast nuclear power plant DCS function verification is achieved. In addition, the invention further discloses a nuclear power plant DCS function verification device and system.

The invention discloses a nuclear power system interdimensional coupling simulation method which includes the steps: firstly, performing modeling on components of a nuclear power system through different reactor thermal hydraulics analysis programs; secondly, preliminarily calculating a reactor thermal hydraulic system analysis program and a reactor thermal hydraulic sub-channel analysis program according to set initial boundary conditions; thirdly, taking calculation results of the reactor thermal hydraulic system analysis program and the reactor thermal hydraulic sub-channel analysis programas boundary conditions of computational fluid dynamics software to perform calculation; fourthly, taking calculation results acquired in the third step as boundary conditions of the reactor thermal hydraulic system analysis program to calculate thermal hydraulic parameters of next time step reactor; fifthly, taking calculation results acquired in the fourth step as boundary conditions of the thermal hydraulic sub-channel analysis program to calculate thermal hydraulic parameters of a reactor core; sixthly, repeating the third step to the fifth step until full time calculation is completed.

The invention discloses a relay module, in particular a relay module with priority control function. The relay module with priority control function comprises a switching value isolated channel, a relay set and a programmable logic device. Input signals are input through the switching value isolated channel, the priority level of the input signals is judged by the programmable logic device, and then the input signals are input to the relay set to control the working state of a rear-end relay set. The relay module can remove the mechanical dithering of the input signals, and the dithering removal time is set according to the requirement of a system; the relay module can output switching value signals according to the priority level of the input signals and the preset logic relationship to control the working state of the rear-end relay; a corresponding relay is selected according to different load categories of relay contacts; and a test interface is also provided for periodical on-line test or off-line test.

The invention discloses a nuclear power plant emergency state auxiliary judgment system and method based on the emergency action level. The nuclear power plant emergency state auxiliary judgment method comprises the steps that the operation state and parameters of a nuclear power plant are automatically obtained by connecting interfaces of a nuclear power plant DSC, a nuclear power plant environment monitoring system and the like and combining an artificial data input module; a logic control module monitors the variation conditions of EAL related parameters in real time, carries out judgment according to built-in logical semantics and gives an EAL logic judgment process and judgment result; through the information such as EAL parameter monitoring, the logic judgment process, the logic judgment result and the suggest emergence state displayed in a visible user interface of the system, a prompt message when a parameter threshold condition is triggered and the emergence state changes is given in time; the system gives emergence state advice, emergence command staff carries out artificial interference, and the final emergence state is determined and issued through a platform. The nuclear power plant emergency state auxiliary judgment system and method based on the emergency action level provide effectively assistance means for correct judgment and decision making of nuclear power plant operators and the emergence command staff.

The invention relates to a special logic control device with a nuclear power set driving stage, which is characterized in that the invention comprises a logic functional module MU, a switch controller VDU, an automatic signal input port A5, a protection signal input port A6, a permitting signal input port A7, an equipment running state signal input port A8, a logic control signal output port OU1 and an equipment running state signal output port OU2, wherein, the switch controller VDU comprises a switch button and a control button. One group of signal input ends of the logic functional module MU are communicated with output ends of the switch button and the control button of the switch controller VDU. One group of signal input ends of the logic functional module MU are communicated with the signal port, and the signal output end is communicated with the logic control signal output port OU1. The equipment running state signal input port A8 is connected with the state testing end of controlled equipment, and the state signal output end of the logic functional module MU is communicated with the equipment running state signal output port OU2. The invention has the effects of clear interface, simple programmed work, easy modification and expansion and small influence among each other. The invention is widely suitable for the automatic logic control of a rear state driving mechanism of a nuclear power station with a stage of 1000mw.

A component interface module (CIM) arbitrates through priority logic component command signals from redundant systems and integrates the selected priority command signal with component feedback signals in component logic to generate a control signal for a component in a complex plant. The non-software based CIM is programmable for use with a variety of plant components. The component logic includes blocking logic that prevents or terminates generation of the control signal such as when component activation has been completed. Diagnostics incorporated into the CIM include: an input port interface test, a pulse test that continuously checks for proper propagation of test pulses through the priority and component logic, and a test of the functioning of the CIM output device such as a relay.

The invention relates to an indicating method for a nuclear power plant back-up control panel, comprising the following steps of: S1, receiving an equipment control signal of a nuclear power plant; S2, carrying out logic processing on the equipment control signal to generate a logic processing result; and S3, outputting an indicating signal of the logic processing result. The invention also relates to an indicating system for the nuclear power plant back-up control panel, comprising a receiving module, a logic processing module and an outputting module, wherein the receiving module is used for receiving the equipment control signal of the nuclear power plant; the logic processing module is used for carrying out logic processing on the equipment control signal to generate the logic processing result; and the outputting module is used for outputting the indicating signal of the logic processing result. By adopting the indicating method and system for the nuclear power plant back-up control panel, provided by the invention, the comprehensive indicating function is realized, the reliability of a nuclear power plant operating function is improved, the equipment fault and the circuit fault are found out in time, the equipment failure operation rate is reduced and the safety is enhanced.

A method and systems of safety analysis of engineering processes for safety analysis of nuclear power stations are disclosed. A distribution of risk factors is analysed on different stages of the engineering process, and safety intervals are determined where safety conditions remain invariable. The method further includes analysis of failure transitions from one safety interval into another by means of cause-effect analysis. Based on the results of this analysis, deterministic safety models are created for possible scenarios of transition of failures from one safety interval into another. The method and systems provide quantitative safety analysis and evaluation for engineering processes in variable safety conditions and enable creating valid safety requirements to perform optimization of an engineering processes control system.

The invention relates to a digital backup panel for a nuclear power plant. The digital backup panel comprises a security-level displayer, a security-level display processor, a non-security-level displayer and a non-security-level display processor. The security-level displayer is connected with a security-level field control equipment cabinet through the security-level display processor and used for displaying and processing security-level instrument control signals. The non-security-level displayer is connected with a non-security-level field control equipment cabinet through the non-security-level display processor and used for displaying and processing non-security-level instrument control signals. According to the digital backup panel, the digital displayer is adopted for changing the graphic display mode of an instrument control system in the traditional simulation technique, the equipment work state can be provided in a centralized mode, the overall occupied space is small, monitoring is centralized, the human-computer interface integration level is high, operators can look for monitoring targets conveniently, and the man-machine load is light. Meanwhile, the security-level displayer and the non-security-level displayer are arranged respectively, and therefore the independence of equipment operation between the security level and the non security level is guaranteed.

The invention is applied to the field of nuclear power control and provides a steam generator water-level control method, device and nuclear power plant of a nuclear power generating unit. The method comprises the following steps of: detecting a parameter associated with steam generator water-level control; obtaining an operation inlet and an equipment operating state associated with the steam generator water-level control; outputting the detected parameter and the obtained operation inlet and equipment operating state to a steam generator water-level control main interface; carrying out functional attribute classification on the detected parameter and the obtained operation inlet and equipment operating state; setting the layout of the steam generator water-level control main interface according to a result of the functional attribute classification; and receiving a steam generator water-level control command and executing the corresponding steam generator water-level control operation. In the embodiment, after the information associated with the steam generator water-level control is functionally classified, the steam generator water-level control main interface is laid out, so that an operator can quickly obtain the parameter in an overall way and realize quick interference.

In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Disclosed herein is an apparatus for reactor power control of a steam turbine power generation system including a reactor, a high-pressure turbine to which steam is supplied from the reactor through a main steam pipe, a low-pressure turbine to which the steam discharged from the high-pressure turbine is supplied via a moisture separator reheater, a branch pipe branched from the main steam pipe to be connected to the moisture separator reheater, a generator connected to the low-pressure turbine, a condenser for condensing the steam discharged from the low-pressure turbine, a condensate pump for feeding condensate condensed by the condenser, and feed water heaters for heating the condensate, the apparatus including a branch pipe control valve provided on the branch pipe and a control unit for controlling an opening degree of the branch pipe control valve.

The invention discloses a device and a method for confirming system testing. The device comprises a testing system and a tested system, wherein the testing system comprises a computer module, a PLC module set, a multi-path distribution module and a multi-path multiplexing module; the computer module is used for issuing a test instruction, displaying and collecting information processed by the tested system and verifying safety and normal running of the tested system with the test instruction; the PLC module comprises a central processing unit and at least two I / O modules; the central processing unit of the PLC module is connected with the computer of the testing system and the I / O module respectively; and the multi-path distribution module and the multi-path multiplexing module are connected with the PLC module and a hard wire on the tested system respectively. By using the multi-path multiplexing module and the multi-path distribution module, the number of the I / O modules in the PLC module is effectively reduced on the premise of not influencing the test effect and the cost of the testing system is reduced.

The invention provides a digital control method and a digital control system of a primary circuit hydrostatic test of a pressurized water reactor nuclear power station, suitable for the nuclear power control field. The method comprises the following steps of: displaying key parameters, a control operation inlet and important alarming related to the primary circuit hydrostatic test on a hydrostatic test control interface; and directly controlling the primary circuit hydrostatic test process through the control operation inlet displayed on the hydrostatic test control interface according to the key parameters displayed by the hydrostatic test control interface. By the method of the invention, the key parameters, the control operation inlet and the important alarming related to the primary circuit hydrostatic test are displayed on the hydrostatic test control interface, and the primary circuit hydrostatic test process is directly controlled through the control operation inlet displayed on the hydrostatic test control interface according to the key parameters displayed by the hydrostatic test control interface, so as to visually and rapidly control the primary circuit hydrostatic test process.

A nuclear power plant and an operation method of the nuclear power plant, which can uprate plant power without greatly modifying the construction of plant equipment, while keeping a core's pressure loss characteristic, a safety margin, and a design margin in the transient state substantially the same as those before the power uprate. Thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam is reduced in the second operation cycle from that in the first operation cycle such that temperature of feedwater discharged from the feedwater heater lowers in the range of 1° C. to 40° C. in the second operation cycle.

The invention relates to an IO (Input / output) to point method and an IO (Input / output) to point for a nuclear power plant simulation platform. The method comprises the following steps of: leading in a new IO list to a database, and setting mark information for storing model label names, expanding and controlling system label names and version numbers in the new IO list; setting the version number of each row of records in the new IO list as n; reading the controlling system label names of each row of records with the version number of n, and each row of records with the version number of n-1, respectively comparing the new IO list with the old IO list according to the size order of the controlling system label names values, judging the types of each row of records, and obtaining model label names, and expanding and controlling system label names according to the types of the records and storing the model label names, and expanding and controlling system label names in the corresponding positions; and updating interface files used by the simulation platform according to the types of the records. The method and the device provided by the invention can automatically compare the records of the IO list, automatically generate and upgrade the interface files, reduce manual to point time, and improve to point accuracy rate.

The invention belongs to the verification technical field of nuclear power stations and particularly relates to a nuclear power station virtual disk table. The disk table comprises a computer server module, an engineer station module, a touch control display operation terminal, and a communication interface module. The computer server module comprises a database module, a thermal hydraulic calculation module and an operation scheduling module. The engineer station module comprises a verification test control module and a disk table frame development module. The touch control display operation terminal includes a disk table frame display module. A touch control operation identification module identifies the button and knob operation executed on the touch control display operation terminal as an operation instruction and then sends the operation instruction to the thermal hydraulic calculation module. The thermal hydraulic calculation module calculates the actual values of the thermal hydraulic parameters of a process system in a nuclear power station and then sends the actual values to the disk table frame display module. The virtual disk table is capable of realizing the virtual functions of the switching among the button operation, the knob operation and the disk table operation, the meter displaying and the like. Meanwhile, the auxiliary design and verification process of the disk table in the nuclear power station can be realized, and the design cycle is shortened.

The invention relates to a virtual roaming design method of a nuclear power plant control room, which comprises the following steps of: setting apparatus layout modeling data of the nuclear power plant control room; setting environment setting modeling data of the nuclear power plant control room; setting evaluation reference data according to the special design analysis and verification procedure requirements for control rooms in codes and standards; and carrying out multiple-scheme interactive simulation on the apparatus layout modeling data and the environment setting modeling data according to the evaluation reference data and analyzing. The invention also relates to a virtual roaming design system of the nuclear power plant control room, which comprises an apparatus layout modeling unit, an environment setting modeling unit, an evaluation system unit and a control judging unit. The invention conducts multiple-scheme interactive simulation verification to the apparatus layout modeling data and the environment setting modeling data of the nuclear power plant control room by using a virtual roaming design, verification investment is low, the combined verification of multiple schemes can be realized, and the implementation time of a control room environment design verification project is shortened.

The invention relates to an alarm inhibition method of a digital alarm system of a nuclear power station, which comprises the steps as follows: 1) function validity confirmation is carried out for an alarm signal produced in the alarm system; 2) when the alarm signal is invalid, the alarm signal is prohibited to trigger an alarm, otherwise, step 3) is carried out; 3) according to the present operating conditions, check is performed to see whether other signals inhibit the alarm signal, thus judging whether the alarm signal needs to be concerned, if not, the alarm signal is inhibited and the related alarm indicators are not triggered. By adopting the digital inhibition method of the digital alarm system of the nuclear power station of the invention, the alarm signal which is not necessarily concerned by an operator can be properly inhabited so that the alarm signal does not appear in the alarm list, which reduces the burden of the operator, improves the working efficiency of the operator and strengthens the safe operation guarantee of the nuclear power station.