122 results about "Reactor protection system" patented technology

Embodiments of the invention disclose a nuclear power plant diversity driving system, a nuclear power plant diversity driving method and a diversity protection system. The nuclear power plant diversity driving system is used for protecting the safety of a nuclear power plant when a reactor protection system fails, and comprises a signal receiving module used for receiving a detection signal, logic processing modules used for logically processing the detection signal to judge whether there is a design basis accident and generating a driving signal when judging that there is a design basis accident, and a signal output module used for outputting the driving signal to an actuator to drive the actuator to act. According to the invention, a design basis accident can be detected automatically, and a driving signal can be generated correspondingly to automatically make the actuator act.

The invention relates to a protecting system of a nuclear power station reactor, comprising at least one lower-layer acquisition device and an upper-layer processing device, wherein the lower-layer acquisition device is connected with an instrument group of the nuclear power station reactor; the instrument group comprises a process measuring instrument and a nuclear instrument; the lower-layer acquisition device acquires and processes a process signal of the process measuring instrument and a nuclear power signal generated by the nuclear instrument, and compares the process signal and the nuclear power signal respectively with a set process signal threshold and a set nuclear power signal threshold to generate digital quantity signals; and the upper-layer processing device is connected with the lower-layer acquisition device and is used for receiving the digital quantity signals generated by the lower-layer acquisition device and carrying out preset logic processing on the digital quantity signals and then generating a shut-down signal and a special driving signal. By carrying out digital processing on a reactor signal, compared with a simulation technique, the implemented protecting system of the nuclear power station reactor has high automation degree and has greater advantages in the aspect of improving usability, reliability, maintainability, economical efficiency, obsolescence resistance and flexibility.

The invention discloses a configuration system for a reactor protection system, which comprises master control software CUTE, a platform PADE used for controlling logical algorithm configuration, a platform SAGE used for configuration displaying in graphs, a software tool DANCE used for downloading and correcting, a software tool PATENT used for parameter setting, and a database management system used for storing defined variables in a project. The platform PADE used for controlling logical algorithm configuration saves algorithm files in the master control software CUTE, the master control software CUTE sends the files to the software tool PATENT used for parameter setting through a CUTE project route, the software tool PATENT used for parameter setting exchanges with the database management system to obtain parameter variables, the database management system sends the parameter variables to the platform SAGE used for configuration displaying in graphs, the platform SAGE used for configuration displaying in graphs visually displays the parameter variables through a screen and also displays information of the CUTE project route, and the master control software CUTE sends downloaded files to the software tool DANCE used for downloading and correcting and implements installment after configuration.

The invention discloses a method for automatically processing safety level DCS response time testing data in a nuclear power station. A simulated condition signal waveform file *.CSV recorded by a waveform recorder is automatically analyzed, and a corresponding phase step response point of each channel in each oscillogram can be determined, so that the response time of each output channel is determined. After multiple *.CSV files recorded under the same working condition are repeatedly analyzed, the files are summarized and screened, and the response time of the current equipment to be detected under the working condition is obtained. Due to computer automation and batch data analysis, a high-efficiency and reliable method is provided for analyzing the response time testing data of a reactor protection system.

The invention relates to a nuclear power plant reactor protection system, comprising a steam turbine protection system and a reactor anticipation transient protection system, wherein the reactor anticipation transient protection system is used for generating an action of controlling the steam turbine protection system during accident conditions; the steam turbine protection system comprises at least three protection channels used for responding a reactor anticipation transient protection signal and generating an action signal for steam turbine stopping protection; a control switch is connected to the reactor anticipation transient protection system and used for distributing the reactor anticipation transient protection signal to each protection channel of the steam turbine protection system; and the steam turbine protection system further comprises a logic control module connected to each protection channel and used for safely stopping a steam turbine when two or more protection channels work. In the nuclear power plant reactor protection system, the unwanted operation rate and the failure operation rate of the interlocking protection action of the reactor anticipation transient protection system and the steam turbine protection system can be maintained to be optimal.

The invention relates to a logic test method and device suitable for a reactor protection system. The logic test method comprises a construction step, a call step, an operation step and a judgment step, wherein the construction step is as follows: constructing test programs and a truth table based on a comma separated values (CSV) format, wherein the truth table comprises the logic diagram index information of the reactor protection system, an input variable, an output variable, the voluation information of the input variable, the input variable of the output variable, and an execution time; the call step is as follows: reading the logic diagram index information, calling the test programs corresponding to the logic diagram index information; the operation step is as follows: reading the input variable and carrying out voluation on the input variable in accordance with the voluation information of the input variable, and carrying out logic operation in accordance with the called test program and the execution time so as to obtain the output value of the output variable; and the judgment step is as follows: judging whether the output value of the output variable is consistent with the expected value, if yes, outputting correct result information, and if no, outputting wrong result information. In the logic test method, the test is carried out by constructing the truth table based on the CSV format and the test program, thus being convenient for modification and regulation, and avoiding human errors.

The application discloses a T3 test loop of a reactor protection system in a nuclear power station and an optimization method thereof. In the optimization method, the T3 test loop employs parallel resistance to check current loop, and comprises a plurality of test switches, wherein at least one test switch is corresponding to a multiple paths of devices, and the at least one test switch has at least two pairs of contact in parallel connection to form parallel contacts. The application has the beneficial effects that: at least two pairs of contact in the test switches are in parallel output to drive the test loop and reduce the risk of maloperation caused by high failure rate of contacts; in one embodiment, nuclear grade relay nodes are connected into the test loop to further improve the reliability of the equipment; in another embodiment, self-locking of test signal is added for interlocking test signal in the case of switch contact failure to reduce the maloperation; and in another embodiment, additional alarm signal sent to a main control enables the normal operation and monitoring on the loop, in order to reduce the risk of refusal-operation caused by scheme optimization.

The invention belongs to reactor design technologies and particularly relates to an emergency shut-down system and method combining activeness and passiveness. The system comprises a control rod emergency shut-down subsystem and an emergency boron injection subsystem. A shut-down breaker of the control rod emergency shut-down subsystem is connected with a reactor protection system, receives emergency shut-down signals sent by the reactor protection system and enables drop of a control rod to be achieved. The emergency boron injection subsystem comprises a concentrated boron storage tank and an injection pump positioned on an injection pipeline, the concentrated boron storage tank is connected with a reactor pressure container and a reactor core through the injection pipeline, and an injection pump control system is connected with the reactor protection system, receives failure-in-achievement emergency shut-down signals sent by the reactor protection system or reactor core neutron flux high signals, and injects concentrated boron into the reactor pressure container and the reactor core. The reliability of the emergency shut-down system under the conditions of accidents is reinforced, and safety of the reactor is improved.

The invention discloses a monitoring mode switching method for a nuclear power plant master control room. The monitoring mode switching method comprises the following steps: judging whether the monitoring mode of a plant computer information and control system (KIC) is available, if not, switching from the monitoring mode of the KIC to the monitoring mode of an auxiliary control panel (ACP); judging whether a common mode fault exists in a plant reactor protection system, if yes, switching from the monitoring mode of the auxiliary control panel to the monitoring mode of a diversity actuation system (DAS). The monitoring mode switching method for the nuclear power plant master control room can efficiently meet the requirement for monitoring under different working conditions during operation of the nuclear power plant; in addition, the invention further discloses a monitoring mode switching system for the nuclear power plant master control room.

Provided is an automated periodic surveillance testing method and apparatus in a digital reactor protection system, which unites a passive testing means such as a self-diagnosis or an on-line state comparison with an active testing means such as an automatic logic test and the like in the digital reactor protection system. Accordingly, a device self-diagnosis, an on-line state diagnosis, and an automatic logic test are used as the automated periodic surveillance testing method in the digital reactor protection system. Thus, the time consumed in a periodic surveillance test can be minimized, thereby saving reactor operating costs, and excessive manpower can be avoided, thereby decreasing potential human errors. Also, a channel detour time at which one of multiple channels is detoured can be minimized based on the automated periodic surveillance test in the digital reactor protection system, thereby enhancing stability.

The invention relates to a protection exit method for a million-kilowatt digital nuclear power plant reactor. A reactor protection system comprises a data collection and processing unit and a logic operation unit, wherein the data collection and processing unit carries out linear conversion, filtering and threshold calculation on signals, then, the processed signals are transmitted to the logic operation unit for carrying out voting logic operation, the logic operation unit is connected with an executing mechanism and is in charge of the action logic management of the executing mechanism, signals generated by the logic operation unit are firstly isolated before the overhaul of a nuclear power plant, and the isolation is removed after the overhaul completion. The protection exit method for the digital nuclear power plant reactor has the advantages that the overhaul construction period is shortened by at least 5 to 10 days, and the misoperation risk of the equipment in the overhaul period is possibly reduced.

The invention relates to a network protocol, in particular relating to a security network protocol for inter-column communication of a system, in particular to a communication method based on a security network protocol for inter-column communication of a reactor protection system. The protection system comprises a communication system among distributed servers, the protocol is composed of a physical layer, a data link layer and an application layer, and the communication method is characterized in that a sending party and a receiving party in network equipment in the security network protocol are in point-to-point connection; and sending and receiving have the same time cycle. By utilizing the communication method, the network transmission is stable, and the communication method further has the specific advantages that as the sending sequences are matched equivalently, the network load is constant, and the safety and real-time property of a network are improved.

The invention belongs to the technical field of nuclear power plant reactor protection, specifically relates to a full-digital reactor protection system debugging device, and aims to develop and design a set of full-digital reactor protection system debugging device, realize batch analog input and digital input / output signal simulation simultaneously by establishing a work condition database quickly, and configure related test conditions according to the test procedures to speed up the progress of debugging. The debugging device is characterized in that the device comprises an upper computer and a plurality of lower computers; the upper computer and the lower computers are connected via the Ethernet; and the lower computers are arranged in a protection channel of a nuclear reactor protection system, and are connected with a DCS cabinet of the reactor protection system through an analog signal cable and a switching signal cable. The efficiency of debugging is improved greatly. The debugging time is shortened. A powerful time support is provided for power generation in power plants.

The invention is applicable to the field of nuclear power station instrument control, and provides a nuclear power station reactor protection system testing method and an apparatus thereof. The method comprises the following steps: triggering a CPU onsite testing signal; triggering a binary testing signal; determine a blocking signal according to the CPU onsite testing signal and the binary testing signal, wherein the CPU onsite testing signal is not always being 0 in the presence of the binary testing signal; determining an action signal according to the binary testing signal; and executing a corresponding operation according to the locking signal and the action signal. The method and the apparatus can reduce the probability of occurrence of misoperation of AV42.

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.

A subcritical reactivity monitor that utilizes one or more primarily gamma sensitive (prompt responding) self-powered detector style radiation measurement devices located within the core of a nuclear reactor to determine the amount that the reactor multiplication factor (Keff) is below the reactivity required to achieve or maintain a self-sustaining nuclear chain reaction. This invention utilizes measured changes in the self-powered detectors' current(s) to allow a reactor operator to measure the value of Keff at essentially any desired interval while the reactor is shutdown with a Keff value less than the critical value of 1.0. This invention will enable integration of the output of the value of Keff directly into the Reactor Protection System, which will enable the elimination of the operational and core design analysis constraint costs associated with the current Boron Dilution Accident prevention methodology and enable automatic control of the Chemical Volume Control System.

The invention relates to a diversified protection device for a fast reactor. The diversified protection device includes: two control cabinets for receiving a safety trigger signal of a reactor, and completing data processing and output; a console for completing a manual driving function; and an engineer station for completing a test and program adjustment and modification of the diversified protection device. The control cabinet comprises a signal distribution device, a data processing device, and a drive device; the signal distribution device receives a signal output by a detector independently arranged or data acquisition hardware of a reactor protection system; the data processing device performs threshold comparison and linkage logic processing on the received signal to generate an automatic driving signal; and two-out-of-two logic is performed, and then the drive device complete a function of a stopping and starting special safety facility. When the reactor protection system failsto give an error command or an abnormal event occurs, the diversified protection device of the present invention can maintain important parameters within a prescribed range to ensure the safety of the reactor.

The invention relates to a nuclear power station double digital quantity output card configuration system and method, wherein the system comprises a first DO card butted with a first CPU (central processing unit), and a second card butted with a second CPU, the first DO card and the second DO card both include relay coils and touch spots, the relay coils are connected with corresponding CPU output ports to form a relay control loop, the touch spots of the first DO card and the second DO card are connected into a system output loop for on-off control, the touch spots of the first DO card and the second DO card are same, and corresponding to fail safe conditions of the system output loop. The invention also provides a nuclear power station digital reactor protection system. According to requirements of the fail safe conditions of the nuclear power station double digital quantity output card configuration system, DO cards with the corresponding type contact spot can be selected, double CPU completely parallel redundancy can be achieved; even if the two CPUs are both in fault, uncontrolled movements affecting equipment and unit safety may appear, and only a failure mode may be produced.

The invention discloses an implementation method for reactor LPD and DNBR on-line protection and monitoring. The method includes the steps that the measured current of self-powered detectors SPND andvarious measured operation parameters of a reactor main coolant system are collected; the collected data is transmitted to an upper calculation unit and a lower calculation unit; the upper calculationunit and the lower calculation unit perform LPD online calculation and DNBR online calculation, wherein the calculation accuracy of the upper calculation unit is higher than that of the lower calculation unit; based on the LDP and DNBR calculation results of the lower calculation unit, LPD and DNBR protection input signals are provided for a reactor protection system to achieve the LPD and DNBR protection function; based on the LDP and DNBR calculation results of the upper calculation unit, the reactor operation status is monitored. By means of the method, the LPD and DNBR distribution of axial sections of each fuel assembly of a reactor core is monitored on line; the LPD and DNBR protection input signals are provided for the reactor protection system, and thus the operation safety and economy of a nuclear power plant are improved.

The invention discloses a nuclear power plant safety level display device, which comprises a human-machine input device, a graph and communication processing module, a power supply module and a display screen, and reserves a maintenance interface. The nuclear power plant safety level display device is applied in a nuclear power plant for providing various safety related parameter information related to a reactor protection system, a post-accident monitoring system and the like to an operator, and supporting the operator to send a control command to a related safety system through the device at the same time. According to the nuclear power plant safety level display device provided by the invention, through the manners such as adopting a simple system structure, selecting low-power consumption components and parts, and optimizing a network topology, the complexity of the nuclear power plant safety level display device is reduced, the power consumption of the whole device is reduced, and a connecting manner of the nuclear power plant safety level display device and a non-safety level system is more reasonable; through a method of combining off-line configuration and on-line running software, all static page processing is put in an off-line configuration part, the calculation processing load of the device is reduced, and the response speed of the device is improved.

A digital protection system includes a process protection system having at least two channels and a reactor protection system having at least two trains. The process protection system includes, in one channel, first and second comparative logic controllers of different types that are mutually independent of each other and that respectively receive process variables as inputs and each outputting comparison logic results. The reactor protection system includes, in one train, first and second concurrent logic controllers of different types that are mutually independent from each other and that respectively receive the comparison logic results as inputs and each outputting concurrent logic results. The reactor protection system includes initiation circuits, each circuit including a plurality of relays connected in series and a plurality of relays connected in parallel. One series-connected relay is controlled by one of the two different concurrent logic results, and one parallel-connected relay is controlled by the other.

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 reactor protection system two-out-of-three conforming maintenance bypass system, comprising a reactor protection system and a 2 / 3 conforming logic bypass unit, wherein the 2 / 3 conforming logic bypass unit comprises a rotary switch S which is provided with four gear contactors and also comprises twelve relays which are all normally open relays. Every four relays of the twelve relays are seen as one group; input ends of input circuits of the four relays of the first group are all connected to first gear contactors, input ends of input circuits of the four relays of the second group are all connected to second gear contactors, and input ends of input circuits of the four relays of the third group are all connected to third gear contactors. According to the system, a bypass device is arranged between a safety monitoring device and a safety logic device so that the protection system maintenance bypass function is added. Device on-line maintenance and test can be achieved; non-planned reactor shutdown probability due to device fault is reduced; the performability of reactors is increased; and production efficiency is guaranteed.

A method is provided for evaluating pellet-cladding interaction (PCI) in a nuclear core having a reactor protection system and a plurality of elongated fuel rods each having fuel surrounded by cladding with a gap therebetween. The method includes: selecting a number of core parameters to be analyzed; evaluating the selected parameters at a plurality of statepoints; generating a model of an operating space of the core based, at least in part, upon the statepoints; selecting a subset or loci of statepoints from the model wherein each of the statepoints of the loci of statepoints, when subjected to a predetermined transient, falls within the operational limits of the reactor protection system; and evaluating the loci of statepoints for PCI in response to the transient. In this manner, the potential for PCI can be accurately determined without requiring every statepoint for every fuel rod in the core to be individually analyzed.

The invention belongs to the technical field of nuclear power station instrument control systems, aims to solve the technical problems that a test probably has safety risks and on-site driving devicesare probably falsely operated in the prior art, and provides a nuclear power station safety-class output control circuit test method and system which are safe and avoid non-disturbance conditions. The test method includes the steps: S1 connecting a maintenance test tool to a periodic test interface device; S2 enabling the periodic test interface device to be powered on before testing, and starting a project to be tested in a test frame; S3 inputting triggering signals on a test panel, and converting the triggering signals into test starting instructions by a control station in a nuclear powerstation reactor protection system; S4 receiving the test starting instructions by a safety-class output control circuit, outputting test detection results by the aid of a pulse mode, and receiving the detection results by the maintenance test tool through the periodic test interface device.

The invention discloses a gas humidity monitoring device for nuclear reactors. The device includes: a cooling control unit for cooling a high-temperature primary loop sampling gas to a certain temperature range; a sampling unit for sampling the cooled gas; and a humidity detection unit for detecting the humidity of gas in the sampling unit. The humidity detection unit includes a humidity sensing component, and a signal conversion circuit which converts an output signal from the humidity sensing component into a signal that can be recognized by a reactor protection system. Collection and conversion of the humidity signals are achieved by a pure-hardware structure, so that reliability demand of security-class equipment is satisfied. The device has high responding speed and achieves zero-emission of radioactive gas.

A communication network for a nuclear power plant protection system includes a plurality of monitoring and control channels, including a first pair of channels which has a first and second channel, the first pair of channels directly communicating through a network of fiber optic data paths with a second pair of channels which has a third channel and a fourth channel; a plurality of engineered safety feature trains, including a first train and a second train, the first train communicating directly with the first pair of channels, and communicating directly with the second train, the second train communicating directly with the second pair of channels, and communicating directly with said first train; a first vital power bus, individually powering the first channel; a second vital power bus, individually powering the second channel, and redundantly powering the first train together with the first vital power bus; a third vital power bus, individually powering the third channel; and a fourth vital power bus, individually powering the fourth channel, and redundantly powering the second train together with the third vital power bus.

The embodiment of the invention relates to the technical field of nuclear power plant reactor protection systems, and discloses a nuclear power plant reactor protection system plate test platform, method and device, a terminal and a storage medium. The method includes the steps of obtaining test parameters, generating a test signal according to the test parameters; injecting the test signal into ato-be-tested plate, and testing the to-be-tested plate; receiving an output feedback signal of the to-be-tested plate through a data acquisition module; and obtaining a test result of the to-be-tested plate according to the output feedback signal. The embodiment of the invention discloses a nuclear power station reactor protection system plate test platform. A test signal is injected into a to-be-tested plate according to test parameters, an output feedback signal of the to-be-tested plate is received, and a test result is obtained according to the output feedback signal to realize offline test of the nuclear power plant reactor protection system plate, thereby realizing plate fault reason positioning, plate performance detection or plate reliability test.