CN217036040U - High temperature gas cooled reactor protection system and wiring terminal row and test device thereof - Google Patents

High temperature gas cooled reactor protection system and wiring terminal row and test device thereof Download PDF

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Publication number
CN217036040U
CN217036040U CN202221024759.XU CN202221024759U CN217036040U CN 217036040 U CN217036040 U CN 217036040U CN 202221024759 U CN202221024759 U CN 202221024759U CN 217036040 U CN217036040 U CN 217036040U
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China
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terminal
protection system
wiring
wiring terminal
electrically connected
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Chinese (zh)
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刘燕
雷川
孟强
郭猛
姜峰
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Huaneng Shandong Shidaobay Nuclear Power Co Ltd
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Huaneng Shandong Shidaobay Nuclear Power Co Ltd
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Abstract

The utility model provides a high-temperature gas cooled reactor protection system, a wiring terminal block and a test device thereof, belonging to the technical field of nuclear power plant reactor protection systems, wherein the wiring terminal block comprises a first wiring terminal, a second wiring terminal, a third wiring terminal and a switching unit; the first connecting terminal is used for being electrically connected with a reactor protection system, the second connecting terminal is used for being electrically connected with an automatic debugging device, and the third connecting terminal is used for being electrically connected with a field instrument/field process equipment; the switching unit selectively electrically connects the first connection terminal with one of the second connection terminal and the third connection terminal. The wiring terminal block can solve the problem that the disconnection, wiring and wiring are required repeatedly during the periodic test of the high-temperature gas-cooled reactor protection system, avoids the risk of accidents caused by misconnection of cables, greatly saves labor and time cost, and effectively improves the working efficiency of the periodic test.

Description

High temperature gas cooled reactor protection system and wiring terminal strip and test device thereof
Technical Field
The utility model belongs to the technical field of reactor protection systems of nuclear power plants, and particularly relates to a high-temperature gas cooled reactor protection system and a wiring terminal strip and a test device thereof.
Background
At present, a wiring terminal block of a high-temperature gas-cooled reactor protection system does not have a switching function. During the periodic test, a signal cable sent to the signal isolation module by the field instrument is released, and is connected with a signal cable of the automatic debugging device, and at the moment, the reactor protection system receives an analog signal sent by the automatic debugging device; and (3) sending the safety trigger module to an instruction output signal line of the field process equipment to be released, establishing connection between the safety trigger module and the automatic debugging device, and acquiring an instruction signal output by the safety trigger module by the automatic debugging device. And after the periodic test is finished, removing the wiring between the reactor protection system and the automatic debugging device, and restoring the wiring with the field instrument and the process equipment.
During the periodic test of the reactor protection system, two cycles of removing normal wiring, terminating the wiring of the automatic debugging device, removing the wiring of the automatic debugging device and recovering the normal wiring are involved, the number of signal cables is large, errors are easy to occur in the process of removing and connecting, in order to avoid accidents caused by the wrong cables, extra wiring correcting work is required after the wiring is completed every time, and the consumed time and the long-acting rate are low.
In order to solve the above problems, it is necessary to provide a protection system for a high temperature gas cooled reactor, a terminal block thereof, and a testing apparatus, which are reasonably designed and can effectively improve the above problems.
SUMMERY OF THE UTILITY MODEL
The utility model aims to at least solve one of the technical problems in the prior art and provides a high-temperature gas-cooled reactor protection system, a wiring terminal block thereof and a test device.
The utility model provides a high-temperature gas cooled reactor protection system wiring terminal block, which comprises a first wiring terminal, a second wiring terminal, a third wiring terminal and a switching unit, wherein the first wiring terminal is connected with the second wiring terminal;
the first connecting terminal is used for being electrically connected with the reactor protection system, the second connecting terminal is used for being electrically connected with the automatic debugging device, and the third connecting terminal is used for being electrically connected with a field instrument/field process equipment; wherein the content of the first and second substances,
the switching unit selectively electrically connects the first connection terminal to one of the second connection terminal and the third connection terminal.
Optionally, during normal operation of the reactor protection system, the switching unit electrically connects the first connection terminal and the third connection terminal;
during the periodic test of the reactor protection system, the switching unit electrically conducts the first connection terminal and the second connection terminal.
Optionally, the switching unit includes a switch.
Another aspect of the utility model provides a protection system for a high temperature gas cooled reactor, the protection system comprising at least one terminal block as described above.
Optionally, the protection system includes a signal isolation module, a protection logic module, and a safety trigger module, which are electrically connected in sequence;
the protection system comprises two wiring terminal rows which are respectively a first wiring terminal row and a second wiring terminal row, wherein the first wiring terminal row corresponds to the signal isolation module, and the second wiring terminal row corresponds to the safety trigger module.
Optionally, the first terminal block is disposed in the signal isolation module, and the second terminal block is disposed in the safety trigger module.
Optionally, in the first terminal block:
the first wiring terminal is electrically connected with the signal isolation module, the second wiring terminal is used for being electrically connected with the automatic debugging device, and the third wiring terminal is used for being electrically connected with the field instrument.
Optionally, in the second terminal block:
the first wiring terminal is electrically connected with the safety trigger module, the second wiring terminal is used for being electrically connected with the automatic debugging device, and the third wiring terminal is used for being electrically connected with the field process equipment.
Another aspect of the present invention provides a periodic testing apparatus for a protection system of a high temperature gas cooled reactor, which includes an automatic debugging apparatus and field instruments/field process equipment, and further includes the wiring terminal block described above, or further includes the protection system described above.
The utility model relates to a high-temperature gas cooled reactor protection system, a wiring terminal block and a test device thereof, wherein the wiring terminal block comprises a first wiring terminal, a second wiring terminal, a third wiring terminal and a switching unit; the first connecting terminal is electrically connected with the reactor protection system, the second connecting terminal is electrically connected with the automatic debugging device, and the third connecting terminal is electrically connected with the field instrument/field process equipment; the switching unit selectively electrically connects the first connection terminal with one of the second connection terminal and the third connection terminal. The connecting terminal block of the high-temperature gas-cooled reactor protection system can solve the problem that the high-temperature gas-cooled reactor protection system needs to be repeatedly disconnected, connected and corrected during a periodic test, avoids the risk of accidents caused by misconnection of cables, greatly saves labor and time cost, and effectively improves the working efficiency of the periodic test.
Drawings
Fig. 1 is a schematic structural diagram of a terminal block according to an embodiment of the utility model;
fig. 2 is a schematic structural diagram of a protection system and a protection device for a high temperature gas cooled reactor according to another embodiment of the present invention.
Detailed Description
In order to make the technical solutions of the present invention better understood, the present invention is further described in detail with reference to the accompanying drawings and the detailed description below.
The high-temperature gas cooled reactor protection system carries out a periodic test during shutdown of a unit according to a nuclear safety related system and equipment periodic test supervision outline, the items comprise a response time measuring test, a protection parameter measuring precision calibration test and an automatic emergency shutdown (two out of four) logic function test, and the test range is from the input end of a signal isolation cabinet to the output end of a safety trigger cabinet.
As shown in fig. 1, an aspect of the present invention provides a terminal block 100 for a protection system of a high temperature gas cooled reactor, where the terminal block 100 includes a first terminal 110, a second terminal 120, a third terminal 130, and a switching unit 140. The first connection terminal 110 is used for electrically connecting with the reactor protection system 200, the second connection terminal 120 is used for electrically connecting with the automatic debugging device 310, and the third connection terminal 130 is used for electrically connecting with the field instrument/field process equipment; the switching unit 140 selectively electrically connects the first connection terminal 110 to one of the second connection terminal 120 and the third connection terminal 130. In this embodiment, the switching unit 130 is a switch, and may also be another switching unit, which is not specifically limited in this embodiment.
During normal operation of the reactor protection system 200, the switching unit 140 electrically connects the first connection terminal 110 and the third connection terminal 130. That is, during normal operation of reactor protection system 200, high temperature gas cooled reactor protection system 200 establishes a signal connection with field instrumentation/field process equipment to ensure that high temperature gas cooled reactor protection system 200 performs its normal function.
During the periodic testing of the reactor protection system 200, the switching unit 140 electrically connects the first connection terminal 110 and the second connection terminal 120. That is, during the periodic test of the reactor protection system 200, the high temperature gas cooled reactor protection system 200 disconnects the signal connection with the field instrument/field process equipment, and establishes the signal connection between the high temperature gas cooled reactor protection system 200 and the automatic debugging device 310, so as to ensure the regular test to be performed normally.
The utility model adopts the wiring terminal strip with the switching unit to replace the existing wiring terminal of the protection system, and the switching unit is arranged at different positions according to requirements to respectively establish the signal connection between the high temperature gas cooled reactor protection system and the automatic debugging device as well as the field instrument/field process equipment. The connecting terminal block of the high-temperature gas-cooled reactor protection system can solve the problem that the high-temperature gas-cooled reactor protection system needs to be repeatedly disconnected, connected and corrected during a periodic test, avoids the risk of accidents caused by misconnection of cables, greatly saves labor and time cost, and effectively improves the working efficiency of the periodic test.
Another aspect of the present invention provides a protection system 200 for a high temperature gas cooled reactor, the protection system 200 comprising at least one terminal block 100 as described above. Specifically, the protection system 200 includes a signal isolation module 210, a protection logic module 220, and a safety trigger module 230, which are electrically connected in sequence, and the protection system 200 includes two terminal blocks 100, i.e., a first terminal block 100a and a second terminal block 100 b. The first terminal block 100a corresponds to the signal isolation module 210, and the second terminal block 100b corresponds to the safety trigger module 230. Further specifically, the first terminal block 100a is disposed in the signal isolation module 210, and the second terminal block 100b is disposed in the safety triggering module 230. The specific structure of the terminal block 100 has been described in detail above, and will not be described in detail herein.
For example, as shown in fig. 2, the first terminal block 100a is disposed in the signal isolation module 210, wherein the first terminal 110 is electrically connected to the signal isolation module 210, the second terminal 120 is electrically connected to the commissioning device 310, and the third terminal 130 is electrically connected to the field instrument 320.
As shown in fig. 2, the second terminal block 100b is disposed in the safety trigger module 230, wherein the first terminal 110 is electrically connected to the safety trigger module 230, the second terminal 120 is electrically connected to the commissioning device 310, and the third terminal 130 is electrically connected to the field process device 330.
According to the high-temperature gas-cooled reactor protection system, the wiring terminal block with the switching unit is arranged on the signal isolation module and the safety trigger module, so that the problems that the wiring, the wiring and the line calibration are required to be repeated during the periodic test of the high-temperature gas-cooled reactor protection system can be solved, the risk of accidents caused by the wrong connection of cables is avoided, the labor and time cost is greatly saved, and the working efficiency of the periodic test is effectively improved.
Another aspect of the present invention provides a periodic testing apparatus 300 for a protection system of a high temperature gas cooled reactor, which includes an automatic commissioning apparatus 310, a field instrument 320, and field process equipment 330, and further includes the terminal block 100 as described above, or further includes the protection system 200 as described above. The specific structures of the terminal block 100 and the protection system 200 have been described in detail above and will not be described in detail herein.
Specifically, during the periodic test of the high temperature gas cooled reactor protection system 200, the high temperature gas cooled reactor protection system 200 needs to establish a connection with the automatic debugging device 310, receive the analog signal sent by the automatic debugging device 310, and send the signal output by the safety trigger module 230 to the automatic debugging device 310 for collection. The terminal block 100 of the present invention is provided with a switching unit 140 having a switching function. During the periodic test, the signal cable sent to the signal isolation module 210 by the field instrument 320 is released, the signal isolation module 210 is connected to the signal cable of the automatic debugging device 310, and at this time, the high temperature gas cooled reactor protection system 200 receives the analog signal sent by the automatic debugging device 310. The command output signal line that sends the safety trigger module 230 to the in-situ process equipment 330 is disconnected, the safety trigger module 230 is connected to the automatic debugging device 310, and the automatic debugging device 310 acquires the command signal output by the safety trigger module 230. After the periodic test is finished, the connection between the reactor protection system 200 of the high temperature gas-cooled reactor and the automatic debugging device 310 is disconnected, and the connection with the field instrument 320 and the field process equipment 330 is restored, so that the reactor protection system 200 of the high temperature gas-cooled reactor can execute normal functions.
More specifically, during the normal operation of the reactor protection system 200, the switching unit 140 electrically connects the first connection terminal 110 and the third connection terminal 130. That is, during normal operation of the reactor protection system 200, the high temperature gas cooled reactor protection system 200 establishes a signal connection with the field instruments 320 or the field process equipment 330 to ensure that the reactor protection system 200 performs normal functions.
During the periodic testing of the reactor protection system 200, the switching unit 140 electrically connects the first connection terminal 110 and the second connection terminal 120. That is, during the periodic test of the reactor protection system 200, the high temperature gas cooled reactor protection system 200 disconnects the signal connection with the field instrument 320 or the field process equipment 330, and establishes the signal connection between the high temperature gas cooled reactor protection system 200 and the automatic debugging device 310, thereby ensuring the regular test to be performed normally.
According to the periodic test device for the high-temperature gas cooled reactor protection system, a first wiring terminal of a wiring terminal row is electrically connected with the high-temperature gas cooled reactor protection system, a second wiring terminal is electrically connected with an automatic debugging device, and a third wiring terminal is electrically connected with a field instrument/field process equipment; the switching unit of the connecting terminal row selectively electrically conducts the first connecting terminal with one of the second connecting terminal and the third connecting terminal; the reactor protection device for the high-temperature gas-cooled reactor can solve the problem that the high-temperature gas-cooled reactor protection system needs to be repeatedly disconnected, connected and corrected during the periodic test, avoids the risk of accidents caused by misconnection of cables, greatly saves labor and time cost, and effectively improves the working efficiency of the periodic test.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the utility model, and these modifications and improvements are also considered to be within the scope of the utility model.

Claims (9)

1. A terminal block of a high-temperature gas cooled reactor protection system is characterized by comprising a first terminal, a second terminal, a third terminal and a switching unit;
the first wiring terminal is used for being electrically connected with the reactor protection system, the second wiring terminal is used for being electrically connected with the automatic debugging device, and the third wiring terminal is used for being electrically connected with a field instrument/field process equipment; wherein the content of the first and second substances,
the switching unit selectively electrically connects the first connection terminal to one of the second connection terminal and the third connection terminal.
2. The terminal block according to claim 1, wherein the switching unit electrically connects the first terminal and the third terminal during normal operation of the reactor protection system;
during the periodic test of the reactor protection system, the switching unit electrically conducts the first connection terminal and the second connection terminal.
3. The terminal block according to claim 2, wherein the switching unit includes a switch.
4. A protection system for a high temperature gas cooled reactor, characterized in that it comprises at least one terminal block according to any one of claims 1 to 3.
5. The protection system according to claim 4, characterized in that the protection system comprises a signal isolation module, a protection logic module and a safety trigger module which are electrically connected in sequence;
the protection system comprises two wiring terminal rows which are respectively a first wiring terminal row and a second wiring terminal row, wherein the first wiring terminal row corresponds to the signal isolation module, and the second wiring terminal row corresponds to the safety trigger module.
6. The protection system of claim 5, wherein the first terminal block is disposed in the signal isolation module and the second terminal block is disposed in the safety trigger module.
7. The protection system according to claim 5, characterized in that in the first terminal block:
the first wiring terminal is electrically connected with the signal isolation module, the second wiring terminal is used for being electrically connected with the automatic debugging device, and the third wiring terminal is used for being electrically connected with the field instrument.
8. The protection system according to claim 5, characterized in that in the second terminal row:
the first wiring terminal is electrically connected with the safety trigger module, the second wiring terminal is used for being electrically connected with the automatic debugging device, and the third wiring terminal is used for being electrically connected with the field process equipment.
9. A periodic test device for a high-temperature gas-cooled reactor protection system, which comprises an automatic debugging device and field instruments/field process equipment, and is characterized by further comprising a wiring terminal block as claimed in any one of claims 1 to 3, or further comprising a protection system as claimed in any one of claims 4 to 6.
CN202221024759.XU 2022-04-29 2022-04-29 High temperature gas cooled reactor protection system and wiring terminal row and test device thereof Active CN217036040U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202221024759.XU CN217036040U (en) 2022-04-29 2022-04-29 High temperature gas cooled reactor protection system and wiring terminal row and test device thereof

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202221024759.XU CN217036040U (en) 2022-04-29 2022-04-29 High temperature gas cooled reactor protection system and wiring terminal row and test device thereof

Publications (1)

Publication Number Publication Date
CN217036040U true CN217036040U (en) 2022-07-22

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Family Applications (1)

Application Number Title Priority Date Filing Date
CN202221024759.XU Active CN217036040U (en) 2022-04-29 2022-04-29 High temperature gas cooled reactor protection system and wiring terminal row and test device thereof

Country Status (1)

Country Link
CN (1) CN217036040U (en)

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