17 results about "Reactor protection system" patented technology

The invention relates to a reactor shutdown method and system, and the method comprises the steps: a reactor protection system receives a monitoring signal and carries out the preprocessing of the monitoring signal, and obtains a preprocessing signal; the reactor protection system is designed by adopting a plurality of safety sequences; the reactor protection system judges whether an emergency shutdown condition is met based on the pre-processing signal; if yes, the reactor protection system outputs a local shutdown signal; if not, not outputting the local shutdown signal; the control rod shutdown subsystem receives the local shutdown signal and cuts off a power supply of a control rod driving system according to the local shutdown signal; and the shutdown rod shutdown subsystem receives the local shutdown signal and cuts off a power supply of the shutdown rod driving system according to the local shutdown signal. According to the invention, the emergency shutdown of the reactor can be rapidly and effectively realized under the accident condition, the influence of common cause failure on the shutdown function can be effectively avoided, and a diversified instrument control system does not need to be designed to cope with the influence of the common cause failure of the reactor protection system.

The invention provides a reliability probability safety evaluation method for a reactor protection system, the method is suitable for the reactor protection system, the reactor protection system comprises at least one first subsystem with a redundant card, and the method comprises the following steps: obtaining modeling input information; calculating the probability of a basic event for modeling according to the modeling input information; a fault tree is established according to the modeling input information, the fault tree comprises a card group common cause failure basic event, and the probability of the card group common cause failure basic event is equal to the sum of the probability of a bus failure basic event and the probability of all types of card common cause failure basic events on a signal flow of at least one first subsystem; the failure probability of the reactor protection system is analyzed using the fault tree and the probability of the elementary events.

The application provides a kind of nuclear power plant reactor protection system driver connection lockout test test method, comprising: when the first test enable signal TE1 of all control preferred module in the control preferred module cabinet to be tested = "1" and the second test enable signal TE2 = "1", after executing a test command, execute the next test command;The read-back information TA and TB of test port are used to read the test feedback state result of all control preferred module in the control preferred module cabinet to be tested;Judge whether the test feedback state result is consistent with the expected result;If not, directly terminate the test, and transmit the abnormal result to the man-machine interface device, so as to prompt the abnormal result on the man-machine interface of the man-machine interface device;If consistent, judge that the test " passes " and transmit the test " passes " result to the man-machine interface device.The application adopts the method of online testing to solve the human error risk caused by manual forced method in traditional control preferred module test.

The present application belongs to the technical field of nuclear power plant instrument control system, and particularly relates to a nuclear power plant state feedback processing system. The present application comprises a turbine bypass system and a reactor protection system, the turbine bypass system sends two signals to the reactor protection system respectively, the reactor protection system is provided with a first logic or and a second logic or, and the two signals are connected with the first logic or and the second logic or respectively. The present application simplifies the design logic, improves the signal response time, and reduces the unplanned shutdown risk caused by the unavailability of the turbine bypass system.

The invention relates to a nuclear power station reactor protection system and a database upgrading method and processing equipment thereof, and the method comprises the steps: S10, reading configuration data of a to-be-upgraded database before upgrading, and storing and recording the configuration data as read data; s20, the specific command signal is locked according to the real-time state of the unit, so that the state of the unit is kept stable; s30, upgrading the configuration signal in the database to be upgraded; s40, reading configuration data of the to-be-upgraded database after upgrading, and recording the configuration data as update data; s50, comparing the read data with the updated data to obtain a comparison result; s60, judging whether upgrading is abnormal or not according to the real-time state of the unit and a comparison result, if yes, executing S70, and if not, executing S80; s70, abnormal warning information is generated; and S80, unlocking the specific command signal. According to the invention, a standardized automatic upgrading scheme is realized, the manual operation amount of workers can be reduced, and the human error risk is reduced.

The embodiment of the invention provides a reactor protection system test method and device, electronic equipment and a storage medium, and belongs to the field of function verification. The method comprises the following steps: acquiring a reactor test script; wherein the reactor test script comprises test input data and expected output data; signal input is carried out on the reactor protection system according to the test input data, so that the reactor protection system triggers a protection action; performing picture collection on the image display through a preset picture collector to obtain a reactor state image; and performing data comparison according to the reactor state image and the expected output data, and determining a test result of the reactor protection system. According to the embodiment of the invention, the reactor protection system can be comprehensively and efficiently tested.

The invention provides an online verification dew-point instrument for a high-temperature gas cooled reactor and a correction method, and the online verification dew-point instrument comprises a temperature and humidity sensor which is used for measuring helium relative humidity data and temperature data of a primary loop of the high-temperature gas cooled reactor, and converting the humidity data and the temperature data into electric signals; the transmitter is connected with the temperature and humidity sensor, and is used for determining dew point temperature data based on the electric signal, then correcting the dew point temperature data by using a preset correction parameter to obtain corrected dew point temperature data, processing the corrected dew point temperature data to obtain a 4-20mA current signal, and sending the 4-20mA current signal to the temperature and humidity sensor; and the 4-20 mA current signal is transmitted to a reactor protection system. According to the technical scheme provided by the invention, a worker can remotely issue the correction parameters to the transmitter through the upper computer, the dew point measurement signal is corrected online in real time, and the problem of measurement drift caused by long-term work of an existing dew point instrument is effectively solved.

The invention belongs to the technical field of response time testing, and particularly relates to a reactor protection system overtemperature monitoring channel response time automatic testing device. Comprising a controller, a relay driving circuit, a relay circuit composed of five relays K2-K6, a resistance circuit composed of six series resistors R1-R6, and a timing circuit, the output of the resistance circuit is connected to a reactor protection system, the output of a shutdown circuit breaker of the reactor protection system is connected to the timing circuit, the controller is connected with the relay driving circuit and the timing circuit, and the relay driving circuit is connected with the controller. The relay driving circuit is connected with the relay circuit, the resistors R1 to R5 are respectively controlled by the opening and closing of the relays K2-K5, and the resistor R6 is controlled by the duplex relay K6. According to the invention, the resistance value of the resistor is changed progressively or progressively on the basis of the original resistance value, so that the condition that the resistance value of the monitoring channel is infinitely great is avoided.

The invention provides a configuration verification method and system for a nuclear power plant reactor protection system and a program product, and the method comprises the steps: obtaining a plurality of card configuration configurations and corresponding test cases, and obtaining FPGA card codes of all cards forming the nuclear power plant reactor protection system, and logic function models of all cards; for each group of card configuration, forming a target model of the nuclear power plant reactor protection system by using the FPGA card code of the target card and the logic function model of the non-target card; performing a simulation test on the target model according to the corresponding test case to obtain actual output data; all the actual output data and expected output data obtained through engineering modeling are compared and analyzed, and a verification analysis result is obtained. According to the method, the card codes of all the cards are alternately verified through the multiple card configuration configurations, dynamic replacement operation and cooperation of the logic function model and the FPGA card codes are achieved, and the efficiency and reliability of design verification are improved.

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

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

The present application belongs to the technical field of reactor trip timing, and particularly relates to a method for connecting the timing of a reactor protection system and an out-of-pile nuclear measurement system, wherein a CH1 channel or a CH2 channel of the out-of-pile nuclear measurement system outputs a threshold trigger signal to an IP channel, an IIP channel, an IIIP channel and an IVP channel of the reactor protection system through a relay parallel photo-coupler isolation connection mode; and a CH1 channel or a CH2 channel of the out-of-pile nuclear measurement system outputs a test or error signal to the IP channel, the IIP channel, the IIIP channel and the IVP channel of the reactor protection system through a relay series photo-coupler isolation connection mode. The method establishes a connection mode of the timing of the source range or the intermediate range of the out-of-pile nuclear measurement system and the reactor protection system, ensures that the timing of the source range or the intermediate range can be triggered correctly, solves the problem of random timing in the traditional connection method, improves the reliability, and adopts a combined connection mode with faster response, and the response time is more optimal.

The application relates to a method and device for testing the response time of a reactor protection system protection signal, computer equipment, a storage medium and a computer program product. The method comprises the following steps: inputting an analog power signal into an analog protection cabinet in the reactor protection system, recording the input time, and obtaining an on-off signal of the analog power signal; outputting a logic setting instruction to a logic protection simulator in the reactor protection system; receiving feedback of the setting logic of a test channel and a non-test channel, when the setting logic of the test channel and the non-test channel meets preset response test logic, inputting the on-off signal into the test channel of a logic protection cabinet in the reactor protection system, and outputting a protection action signal to a signal collector in the reactor protection system; outputting a signal output instruction to the signal collector; acquiring a protection action signal trigger time, and obtaining a total response time. The method can efficiently test the response time of the reactor protection system protection signal.

The invention discloses a T1 periodic test interface device of a reactor protection system, and relates to the technical field of interface tests. Comprising a fixing frame, a vertical plate arranged on one side of the fixing frame, a second protruding block arranged on the inner side of the fixing frame, a first connecting rod arranged at the end of the second protruding block, a second connecting rod arranged at the end of the first connecting rod and a rotary knob arranged at the end of the second connecting rod. And the second limiting plate is arranged on the end face of the vertical plate. The PIPS terminal unit has the beneficial effects that a plurality of groups of connecting wires at the end part of the PIPS terminal unit can be arranged through the arranged wire pipes, so that the orderliness of lines in the cabinet main body is ensured; the arranged clamping unit can quickly clamp and fix a wire pipe, and the stability of a circuit is ensured; the installation unit is matched with the PIPS terminal unit, so that an operator can conveniently install the PIPS terminal unit on the inner side of the cabinet main body, and the device is simple in structure and convenient to operate.

The application relates to a channel precision, response time and protection setting value automatic testing device of a nuclear power plant reactor protection system based on a NASPIC platform, and particularly relates to a nuclear power plant reactor protection system testing device. Field instruments or sensors are simulated, signals are injected into a NASPIC platform safety level DCS system port, corresponding output signals of the safety level DCS system are collected, data of a safety level DCS engineer station are acquired, comparison or logical operation is carried out, and a corresponding test report is generated. The application realizes a reactor protection system regular test automatic testing technology based on the NASPIC platform, can greatly shorten a test time, improve work efficiency and reduce human errors.

The application discloses a control system and a control method for debugging of an emergency diesel generator of a nuclear power plant, and the control system comprises a diesel generator, an analog DCS control device, an on-site control system of a diesel generator set, a medium-voltage circuit breaker, a shutdown mechanism and a plurality of hot standby devices; the analog DCS control device is integrated with control logic of process information and control systems, safety level interface control systems, process automation systems, safety automation systems and reactor protection systems in the nuclear power plant, so that when the process information and control systems, the safety level interface control systems, the process automation systems, the safety automation systems and the reactor protection systems in the nuclear power plant are unavailable, the debugging of the emergency diesel generator can still be normally carried out.