CN111326267A - Nuclear power station safety instrument control system response time measuring device and measuring method thereof - Google Patents
Nuclear power station safety instrument control system response time measuring device and measuring method thereof Download PDFInfo
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- CN111326267A CN111326267A CN202010175638.4A CN202010175638A CN111326267A CN 111326267 A CN111326267 A CN 111326267A CN 202010175638 A CN202010175638 A CN 202010175638A CN 111326267 A CN111326267 A CN 111326267A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention belongs to the technical field of nuclear power station safety instrument control systems, and particularly relates to a device and a method for measuring response time of a nuclear power station safety instrument control system, wherein the device comprises the following steps: the system comprises an operation display unit, a plurality of processor units, a selection output unit, a signal conditioning unit, a time acquisition unit, a safety instrument control system protection channel cabinet and a safety instrument control system special cabinet; the operation display unit is respectively connected with each processor unit; each processor unit is also connected with a selection output unit, each selection output unit is connected with a safety instrument control system protection channel cabinet, and a time acquisition unit and a signal conditioning unit are arranged in each safety instrument control system protection channel cabinet; each signal conditioning unit is also connected with each selection output unit; and the two selective output units are respectively connected with a special cabinet for a safety instrument control system.
Description
Technical Field
The invention belongs to the technical field of nuclear power station safety instrument control systems, and particularly relates to a device and a method for measuring response time of a nuclear power station safety instrument control system.
Background
The response time of the nuclear power station safety instrument control system comprises reactor shutdown response time and action response time of a special safety facility. In order to ensure that a reactor of a nuclear power station can be stopped safely and reliably in time in an emergency, the reactor stopping response time and the action response time of a special safety facility need to be measured regularly, so that the response time can meet the requirements of technical specifications, and the good performance of equipment such as a transmission clamping piece, a processor and the like in each link of a loop can be ensured.
The reactor trip signal response time is the time from the generation of the initial trip signal to the output of the downstream trip command. When two or more initial shutdown signals of the four channels reach the threshold value of the protection signal due to the change of the process parameters related to the shutdown of the nuclear power station, the shutdown signals are triggered after being processed by the processor, the shutdown command is transmitted to the shutdown circuit breaker to disconnect the shutdown circuit breaker, and the downstream control rods lose power supply and fall into the bottom of the reactor core to realize the shutdown of the reactor. The response time of the safety special equipment action signal is measured from the time when the process parameter triggering the safety special equipment action changes to the time when the safety special equipment cabinet outputs the equipment action command. The reactor protection cabinet generates local special safety facility action signals and sends the signals to the safety special cabinet for voting, when more than two action signals are effective, real special action signals are output, and finally, a command is output from a CIM board card of the special safety system to drive the local equipment to act.
At present, when response time of a nuclear power station safety instrument control system is measured by using a waveform recorder, a corresponding signal is added to a terminal at the input side of a reaction protection cabinet of the safety instrument control system through a signal generator, time from input signal jump to output command trigger is measured, about 150 response time working conditions need to be measured for one unit of a certain nuclear power station, each working condition has 4 input signals, each signal needs to be measured for 3 times, the waveform recorder is used for measuring the time which needs to be manually added for about 1800 times, meanwhile, the waveform recorder is used for manually positioning signals and calculating, and the whole process consumes a large amount of time and manpower. Because the cabinets of the safety instrument control system are distributed in 6 rooms with different heights, each room is physically isolated, when the waveform recorder is used, a signal input cable and a time acquisition cable need to be laid across the rooms temporarily each time, and the preparation and recovery time before and after each test is long, so that the working efficiency is low; when the waveform recorder is used, the formal wiring on the terminal row in the safety instrument control system cabinet needs to be disconnected before testing every time, the risk of terminal damage is increased and the risk of wiring recovery errors is increased due to frequent disconnection, and hidden dangers are brought to debugging and running of a nuclear power station.
Therefore, in order to solve the problems of the conventional measurement method, a set of simple, convenient and efficient special time measuring device needs to be designed to improve the working efficiency of measurement and reduce human errors, and meanwhile, the cabinet equipment of the safety instrument control system is prevented from being damaged during the test.
Disclosure of Invention
The invention aims to design a device and a method for measuring the response time of a nuclear power station safety instrument control system, which are used for solving the technical problems that the measurement of a waveform recorder in the prior art needs manual measurement, consumes time and labor, and causes hidden dangers to the debugging and the operation of a nuclear power station due to terminal damage, wiring recovery errors and the like caused by frequent wire disconnection.
The technical scheme of the invention is as follows:
a nuclear power plant safety instrumentation control system response time measuring device includes: the system comprises an operation display unit 1, a plurality of processor units 2, a selection output unit 3, a signal conditioning unit 4, a time acquisition unit 5, a safety instrument control system protection channel cabinet 6 and a safety instrument control system special cabinet 7; the operation display unit 1 is respectively connected with each processor unit 2; each processor unit 2 is also connected with a selection output unit 3, each selection output unit 3 is connected with a safety instrument control system protection channel cabinet 6, and a time acquisition unit 5 and a signal conditioning unit 4 are arranged in each safety instrument control system protection channel cabinet 6; each signal conditioning unit 4 is also connected with each selection output unit 3; and the two selective output units 3 are also respectively connected with a safety instrument control system special cabinet 7.
The operation display unit 1 is used for sending signals to the processor unit; the operation display unit 1 is also connected to each time acquisition unit 5 for reading and displaying the response time values recorded in the time acquisition unit 5.
The processor unit 2 is used for receiving a command issued by the operation display unit 1, and the processor unit 2 outputs an operation result to the selection output unit 3;
the selection output unit 3 is used for receiving the operation result signal of the processor unit 2, switching and selecting signals required to be output under different working conditions during the test period, and sending the output signals to the signal conditioning unit 4.
The signal conditioning unit 4 conditions the acquired signal into a standard 1-5V voltage signal, and the conditioned voltage signal is sent to the time acquisition unit 5 for acquisition; the time acquisition unit 5 is composed of four high-precision acquisition cards which are communicated with each other to ensure the time synchronization of the four acquisition cards, and the acquisition cards acquire the triggering time of signals from the signal conditioning unit 4 and send the time to the operation display unit 1.
The number of the processor unit 2, the selection output unit 3, the signal conditioning unit 4, the time acquisition unit 5 and the safety instrument control system protection channel cabinet 6 is four respectively.
The number of the safety instrument control system special equipment cabinets 7 is two.
The method for measuring the response time of the nuclear power station safety instrument control system comprises the following steps:
the method comprises the following steps: the operation display unit 1 sends a command to the processor unit 2 to establish a non-shutdown state of the safety instrument control system; the processor unit 2 carries out operation after receiving the command, and outputs a protection threshold signal to the selection output unit 3 after operation;
step two: the selective output unit 3 transmits the output signal of the device to a safety instrument control system protection channel cabinet 6 and a safety instrument control special cabinet 7 through hard wiring, and simultaneously transmits the output signal to the signal conditioning unit 4 for collection; the signal conditioning unit 4 sends the signal from the selection output unit 3 to the time acquisition unit 5 for time recording, and the time is defined as T1;
step three: the safety instrument control system protection channel cabinet 6 and the safety instrument control system special cabinet 7 perform two-out-of-four operation according to the signals sent by the selection output unit 3, after the operation, the shutdown and safety special command signals are sent to the signal conditioning unit 4, after the signal conditioning unit conditions, the signals are sent to the time acquisition unit 5 for time acquisition, and at the moment, the time is defined as T2;
step four: the time acquisition unit 5 sends the acquired T1 and T2 time to the operation display unit 1; the operation display unit 1 performs difference calculation on the T2 and T1 values, compares the difference with a criterion value, and if the time difference is less than or equal to the criterion value, the result is qualified;
step five: after the test, the operation display unit 1 stops issuing the command, and the safety instrument control system cabinet does not receive the signal of the test device any more; and (4) removing the connection between the test device and the safety instrument control system, recovering the safety instrument control system to the initial state, and finishing the test.
The invention has the beneficial effects that:
1. the response time measuring device of the nuclear power station safety instrument control system designed by the invention has high automation degree and improves the working efficiency: by applying the response time measuring device, the automatic injection of the test signal to the tested device and the automatic acquisition and calculation of the response time are realized, and various complicated manual operations of a waveform recorder are avoided. The working efficiency is greatly improved.
2. Reduce repetitive work and human error risk: the wiring port of the device can be directly plugged into and pulled out of the terminal strip of the safety instrument control system cabinet, a tool is connected with a tested system before a test, signal wiring is not required to be operated during the test, compared with a measurement mode using a waveform recorder, the device saves the work of repeatedly disconnecting the wiring during the test, and reduces the risk of human errors such as short circuit grounding, disconnection errors and the like caused during disconnection.
3. Avoiding extensive cross-room cabling and termination: the time acquisition units are respectively arranged in the four safety instrument control system protection channel cabinets of the measuring device, and the four protection channels are in communication connection, so that the condition that the four protection channels transmit time acquisition signals to one cabinet for acquisition in a hard wiring mode is avoided, and a large number of cross-room cables are laid and terminated.
Drawings
Fig. 1 is a signal flow diagram of a device for measuring response time of a nuclear power plant safety instrument control system according to the present invention.
Wherein: 1-an operation display unit; 2-a processor unit; 3-selecting an output unit; 4-a signal conditioning unit; 5-a time acquisition unit; 6, protecting the channel cabinet by the safety instrument control system; 7, the safety instrument control system is specially provided with a cabinet.
Detailed Description
The invention will be further described with reference to the following figures and examples:
the invention relates to a response time measuring device of a nuclear power station safety instrument control system, in particular to a device which is characterized in that four channels of the safety instrument control system are respectively provided with a cabinet, and each cabinet is internally provided with a time acquisition unit part; a safety instrument control system is specially provided with an A/B row room which is respectively provided with a cabinet, and corresponding time signals are sent to four channels for collection. An operation display unit is additionally arranged. The detailed structure of the device is shown in figure 1
The device adds signals to a terminal inlet of a safety instrument control system cabinet through different types of output board cards (DO switching value output, AO analog quantity output and RO temperature resistance value output) in six cabinets, the signals can output shutdown and safety special instructions after operation processing, and a time acquisition unit of the device can acquire the time of the signal inlet of the safety instrument control system and the time of instruction output.
The measuring device is characterized in that a time acquisition unit is respectively arranged in the four safety instrument control channel special tool cabinets, the four time acquisition units are communicated with each other, each acquisition unit can realize acquisition of signals of the channel and acquisition of safety special signal action time, and by adopting the design mode, a large amount of cable laying and termination among the four channels of the safety instrument control system can be omitted.
The device is specifically applied in a mode that firstly, the device establishes a non-reactor-tripping operation environment by simulating a nuclear power station power operation platform signal, then the device triggers corresponding logical actions of a reactor protection channel and a safety special channel through the change of a simulation signal, calculates the time of the reactor shutdown and the safety special action of a safety instrument control system by collecting the change time of the simulation signal and the command time of the reactor shutdown and the safety special action, compares the calculated response time with a criterion value, and judges that the response time meets the requirement if the measured time is less than or equal to the criterion time.
The specific embodiment is as follows: a nuclear power plant safety instrumentation control system response time measuring device includes: the system comprises an operation display unit 1, a plurality of processor units 2, a selection output unit 3, a signal conditioning unit 4, a time acquisition unit 5, a safety instrument control system protection channel cabinet 6 and a safety instrument control system special cabinet 7; the operation display unit 1 is respectively connected with each processor unit 2; each processor unit 2 is also connected with a selection output unit 3, each selection output unit 3 is connected with a safety instrument control system protection channel cabinet 6, and a time acquisition unit 5 and a signal conditioning unit 4 are arranged in each safety instrument control system protection channel cabinet 6; each signal conditioning unit 4 is also connected with each selection output unit 3; and the two selective output units 3 are also respectively connected with a safety instrument control system special cabinet 7.
The operation display unit 1 is used for sending signals to the processor unit; the operation display unit 1 is also connected to each time acquisition unit 5 for reading and displaying the response time values recorded in the time acquisition unit 5.
The processor unit 2 is used for receiving a command issued by the operation display unit 1, and the processor unit 2 outputs an operation result to the selection output unit 3;
the selection output unit 3 is used for receiving the operation result signal of the processor unit 2, switching and selecting signals required to be output under different working conditions during the test period, and sending the output signals to the signal conditioning unit 4.
The signal conditioning unit 4 conditions the acquired signal into a standard 1-5V voltage signal, and the conditioned voltage signal is sent to the time acquisition unit 5 for acquisition; the time acquisition unit 5 is composed of four high-precision acquisition cards which are communicated with each other to ensure the time synchronization of the four acquisition cards, and the acquisition cards acquire the triggering time of signals from the signal conditioning unit 4 and send the time to the operation display unit 1.
The number of the processor unit 2, the selection output unit 3, the signal conditioning unit 4, the time acquisition unit 5 and the safety instrument control system protection channel cabinet 6 is four respectively.
The number of the safety instrument control system special equipment cabinets 7 is two.
The method for measuring the response time of the nuclear power station safety instrument control system comprises the following steps:
the method comprises the following steps: the operation display unit 1 sends a command to the processor unit 2 to establish a non-shutdown state of the safety instrument control system; the processor unit 2 carries out operation after receiving the command, and outputs a protection threshold signal to the selection output unit 3 after operation;
step two: the selective output unit 3 transmits the output signal of the device to a safety instrument control system protection channel cabinet 6 and a safety instrument control special cabinet 7 through hard wiring, and simultaneously transmits the output signal to the signal conditioning unit 4 for collection; the signal conditioning unit 4 sends the signal from the selection output unit 3 to the time acquisition unit 5 for time recording, and the time is defined as T1;
step three: the safety instrument control system protection channel cabinet 6 and the safety instrument control system special cabinet 7 perform two-out-of-four operation according to the signals sent by the selection output unit 3, after the operation, the shutdown and safety special command signals are sent to the signal conditioning unit 4, after the signal conditioning unit conditions, the signals are sent to the time acquisition unit 5 for time acquisition, and at the moment, the time is defined as T2;
step four: the time acquisition unit 5 sends the acquired T1 and T2 time to the operation display unit 1; the operation display unit 1 performs difference calculation on the T2 and T1 values, compares the difference with a criterion value, and if the time difference is less than or equal to the criterion value, the result is qualified;
step five: after the test, the operation display unit 1 stops issuing the command, and the safety instrument control system cabinet does not receive the signal of the test device any more; and (4) removing the connection between the test device and the safety instrument control system, recovering the safety instrument control system to the initial state, and finishing the test.
The present invention has been described in detail with reference to the drawings and examples, but the present invention is not limited to the examples, and various changes can be made within the knowledge of those skilled in the art without departing from the spirit of the present invention. The prior art can be adopted in the content which is not described in detail in the invention.
Claims (7)
1. A nuclear power station safety instrument control system response time measuring device is characterized by comprising: the system comprises an operation display unit (1), a plurality of processor units (2), a selection output unit (3), a signal conditioning unit (4), a time acquisition unit (5), a safety instrument control system protection channel cabinet (6) and a safety instrument control system special cabinet (7); the operation display unit (1) is respectively connected with each processor unit (2); each processor unit (2) is also connected with a selection output unit (3), each selection output unit (3) is connected with a safety instrument control system protection channel cabinet (6), and a time acquisition unit (5) and a signal conditioning unit (4) are arranged in each safety instrument control system protection channel cabinet (6); each signal conditioning unit (4) is also connected with each selection output unit (3); wherein, the two selective output units (3) are respectively connected with a special cabinet (7) of a safety instrument control system.
2. The nuclear power plant safety instrumentation and control system response time measuring device of claim 1, wherein: the operation display unit (1) is used for sending signals to the processor unit; the operation display unit (1) is also connected with each time acquisition unit (5) and is used for reading and displaying the response time value recorded in the time acquisition unit (5).
3. The nuclear power plant safety instrumentation and control system response time measuring device of claim 2, wherein: the processor unit (2) is used for receiving a command issued by the operation display unit (1), and the processor unit (2) outputs an operation result to the selection output unit (3); the selection output unit (3) is used for receiving the operation result signal of the processor unit (2), switching and selecting signals required to be output under different working conditions during the test period, and sending the output signals to the signal conditioning unit (4).
4. The nuclear power plant safety instrumentation and control system response time measuring device of claim 1, wherein: the signal conditioning unit (4) conditions the acquired signal into a standard 1-5V voltage signal, and the conditioned voltage signal is sent to the time acquisition unit (5) for acquisition; the time acquisition unit (5) is composed of four high-precision acquisition cards which are communicated with each other to ensure the time synchronization of the four acquisition cards, and the acquisition cards acquire the triggering time of signals from the signal conditioning unit (4) and send the time to the operation display unit (1).
5. The nuclear power plant safety instrumentation and control system response time measuring device of claim 4, wherein: the number of the processor unit (2), the selection output unit (3), the signal conditioning unit (4), the time acquisition unit (5) and the safety instrument control system protection channel cabinet (6) is four respectively.
6. The nuclear power plant safety instrumentation and control system response time measuring device of claim 5, wherein: the number of the special cabinets (7) for the safety instrument control system is two.
7. The method for measuring the response time of the nuclear power plant safety instrumentation and control system according to any one of claims 1 to 6, comprising the steps of:
the method comprises the following steps: the operation display unit (1) issues a command to the processor unit (2) to establish a non-shutdown state of the safety instrument control system; the processor unit (2) performs operation after receiving the command, and outputs a protection threshold signal to the selection output unit (3) after the operation;
step two: the selective output unit (3) transmits the output signal of the device to a safety instrument control system protection channel cabinet (6) and a safety instrument control special cabinet (7) through hard wiring, and simultaneously transmits the output signal to the signal conditioning unit (4) for collection; the signal conditioning unit (4) sends the signal from the selection output unit (3) to the time acquisition unit (5) for time recording, and the time is defined as T1;
step three: the safety instrument control system protection channel cabinet (6) and the safety instrument control system special cabinet (7) perform two-out-of-four operation according to the signals sent by the selection output unit (3), shutdown and safety special command signals are sent to the signal conditioning unit (4) after the operation, the signals are sent to the time acquisition unit (5) for time acquisition after the signal conditioning unit conditions, and the time is defined as T2；
Step four: the time acquisition unit (5) acquires the acquired T1And T2Time is sent to the operation display unit 1; operation display unit (1) for T2And T1Performing difference calculation on the values, comparing the difference value with a criterion value, and if the time difference value is less than or equal to the criterion value, determining that the result is qualified;
step five: after the test, the operation display unit (1) stops issuing commands, and the safety instrument control system cabinet does not receive signals of the test device any more; and (4) removing the connection between the test device and the safety instrument control system, recovering the safety instrument control system to the initial state, and finishing the test.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112562878A (en) * | 2020-11-25 | 2021-03-26 | 三门核电有限公司 | Nuclear power plant reactor protection and monitoring system response time measuring device and method |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN112562878A (en) * | 2020-11-25 | 2021-03-26 | 三门核电有限公司 | Nuclear power plant reactor protection and monitoring system response time measuring device and method |
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