CN112102977A - Nuclear reactor safety rod performance test system - Google Patents
Nuclear reactor safety rod performance test system Download PDFInfo
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- CN112102977A CN112102977A CN202010925846.1A CN202010925846A CN112102977A CN 112102977 A CN112102977 A CN 112102977A CN 202010925846 A CN202010925846 A CN 202010925846A CN 112102977 A CN112102977 A CN 112102977A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/08—Structural combination of reactor core or moderator structure with viewing means, e.g. with television camera, periscope, window
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/12—Sensitive element forming part of control element
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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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
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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
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- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to the technical field of space nuclear reactor measurement and control, and particularly discloses a nuclear reactor safety rod performance testing system which comprises an industrial control computer, a control cabinet, a safety rod driving mechanism and a safety rod assembly, wherein the industrial control computer is connected with the control cabinet; the control cabinet comprises a UPS power supply module, a motor driving module, a rotation angle acquisition module, a photoelectric coding acquisition module, an electromagnetic card lock control circuit and an electromagnetic clutch control circuit, wherein the motor driving module, the rotation angle acquisition module, the photoelectric coding acquisition module, the electromagnetic card lock control circuit and the electromagnetic clutch control circuit are respectively connected with the UPS power supply module; the safety rod driving mechanism comprises a stepping motor, an electromagnetic clutch and an electromagnetic card lock; the output shaft of the safety rod driving mechanism is provided with a rotary transducer and a light-coded transducer, and the output shaft of the stepping motor is in transmission connection with the safety rod assembly. The nuclear reactor safety rod performance test system can test rod falling time, is simple and convenient to operate, is safe and reliable, and is beneficial to guaranteeing the personal safety of testers.
Description
Technical Field
The invention relates to the technical field of space nuclear reactor measurement and control, in particular to a nuclear reactor safety rod performance test system.
Background
The safety rod system of the nuclear reactor is used as a key device for reliable operation and safe fast shutdown of a space nuclear energy system, and has the main function of being used for fast rod falling and shutdown of the reactor. Before the space nuclear power device carries out space flight tests, a ground prototype must be developed and tested, and the performance and reliability of the safety rod system and all components in the set service life of the tests and the test of the rapid rod falling time under various working conditions are verified.
Because the working environment condition of the space nuclear reactor safety rod system is extremely harsh, the technical requirement of the system is strict, the structure is precise and complex, the manufacturing and the test are both for the first time in China, no reference experience exists, and the comprehensive difficulty of the test and the verification is very high. Therefore, it is necessary to design a performance testing system for a nuclear reactor safety rod, which is used for efficiently testing the working performance and the rapid rod-falling time of the safety rod system in severe environments such as high temperature, earthquake and the like.
Disclosure of Invention
In order to solve the technical problems, the invention mainly aims to provide a performance testing system for a safety rod of a nuclear reactor.
The utility model provides a nuclear reactor safety stick capability test system, the system includes industrial control computer, control cabinet, safety stick actuating mechanism and safety stick subassembly, wherein: the industrial control computer is connected with the control cabinet;
the control cabinet comprises a UPS power supply module, a motor driving module, a rotation angle acquisition module, a photoelectric coding acquisition module, an electromagnetic card lock control circuit and an electromagnetic clutch control circuit, wherein the motor driving module, the rotation angle acquisition module, the photoelectric coding acquisition module, the electromagnetic card lock control circuit and the electromagnetic clutch control circuit are respectively connected with the UPS power supply module;
the safety rod driving mechanism comprises a stepping motor, an electromagnetic clutch and an electromagnetic card lock; a rotary change sensor and a light coding sensor are mounted on an output shaft of the safety rod driving mechanism, the rotary change sensor is electrically connected with the rotary change angle acquisition module, and the light coding sensor is electrically connected with the photoelectric coding acquisition module; the motor driving module is electrically connected with the stepping motor; the electromagnetic card lock control circuit is electrically connected with the electromagnetic card lock; the electromagnetic clutch control circuit is electrically connected with the electromagnetic clutch; the electromagnetic clutch and the electromagnetic clamp lock are arranged on an output shaft of the safety rod driving mechanism; the output shaft of the stepping motor is in transmission connection with the safety rod assembly.
Further, the system still includes the exhaust subassembly that fills, fills the exhaust subassembly and includes gas charging valve, exhaust valve and pressure sensor, wherein:
the control cabinet also comprises an inflation and exhaust valve control circuit and a pressure acquisition module, wherein the inflation and exhaust valve control circuit is electrically connected with the inflation valve and the exhaust valve; the pressure acquisition module is electrically connected with the pressure sensor.
Furthermore, the control cabinet further comprises a motor temperature acquisition module, the safety rod driving mechanism further comprises a temperature sensor installed on the stepping motor, and the motor temperature acquisition module is electrically connected with the temperature sensor.
Furthermore, the control cabinet further comprises an electromagnetic card lock voltage and current acquisition module and an electromagnetic clutch voltage and current acquisition module, the electromagnetic card lock voltage and current acquisition module is electrically connected with the electromagnetic card lock, and the electromagnetic clutch voltage and current acquisition module is electrically connected with the electromagnetic clutch.
Furthermore, the industrial control computer comprises a computer and a data interface acquisition card, and the computer is connected with the control cabinet through the data interface acquisition card; wherein:
the computer stores computer instructions, and the computer instructions are operated to process the acquisition information of the rotation angle acquisition module, the photoelectric coding acquisition module, the pressure acquisition module, the motor temperature acquisition module, the electromagnetic card lock voltage and current acquisition module and the electromagnetic clutch voltage and current acquisition module and send control signals to the motor driving module, the electromagnetic card lock control circuit, the electromagnetic clutch control circuit and the charging and discharging valve control circuit.
Further, the data interface acquisition card comprises a PCI-to-serial port board card, an analog input board card, a digital output board card and a motor drive board card, wherein:
the PCI serial port board card is connected with the motor temperature acquisition module and the rotation angle acquisition module;
the analog input board card is connected with the pressure acquisition module, the electromagnetic card lock voltage and current acquisition module and the electromagnetic clutch voltage and current acquisition module; the digital quantity output board card is connected with the electromagnetic card lock control circuit, the electromagnetic clutch control circuit and the charging and discharging valve control circuit; the motor drive board card is connected with the motor drive module and the photoelectric code acquisition module.
Furthermore, the electromagnetic clutch control circuit, the electromagnetic lock control circuit and the charging and discharging valve control circuit are all provided with magnetic latching relays.
Furthermore, a communication interface is arranged on the UPS module and is connected with the industrial control computer through the communication interface.
Furthermore, the distance between the control cabinet and the safety rod driving mechanism is 18-20 m.
Furthermore, the industrial control computer, the control cabinet and the safety rod driving mechanism are sequentially connected through the beam splitting shielded cable.
The nuclear reactor safety rod performance test system can safely and efficiently monitor the working performance of the safety rod assembly in various complex environments through the operation and operation of the industrial control computer, test the rod falling time, is simple and convenient to operate, is safe and reliable, and is beneficial to ensuring the personal safety of testers; on the other hand, the system is the first time of industry in China for the performance test of the nuclear reactor safety rod, and has very high popularization value.
Drawings
FIG. 1 is a structural composition diagram of a nuclear reactor safety rod performance testing system according to an embodiment of the present invention;
wherein: 1-industrial control computer, 101-computer, 102-data interface acquisition card, 1021-PCI (peripheral component interconnect) to serial port card, 1022-analog input card, 1023-digital output card, 1024-motor drive card, 2-control cabinet, 201-UPS power module, 202-motor drive module, 203-rotation angle acquisition module, 204-photoelectric coding acquisition module, 205-electromagnetic card lock control circuit, 206-electromagnetic clutch control circuit, 207-charging and discharging valve control circuit, 208-pressure acquisition module, 209-motor temperature acquisition module, 210-electromagnetic card lock voltage and current acquisition module, 211-electromagnetic clutch voltage and current acquisition module, 3-safety rod drive mechanism, 301-stepping motor, 302-electromagnetic clutch, electromagnetic clutch, 303-electromagnetic latch, 304-rotation sensor, 305-optical coding sensor, 306-temperature sensor, 4-safety rod component, 5-inflation and exhaust component, 501-inflation valve, 502-exhaust valve and 503-pressure sensor.
The implementation, functional features and advantages of the objects of the present invention will be further explained with reference to the accompanying drawings.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
The invention provides a nuclear reactor safety rod performance test system, as shown in figure 1, the system comprises an industrial control computer 1, a control cabinet 2, a safety rod driving mechanism 3 and a safety rod assembly 4, wherein: the industrial control computer 1 is connected with the control cabinet 2; the control cabinet 2 comprises a UPS power supply module 201, and a motor driving module 202, a rotation angle acquisition module 203, a photoelectric code acquisition module 204, an electromagnetic lock control circuit 205 and an electromagnetic clutch control circuit 206 which are respectively connected with the UPS power supply module 201; the safety rod driving mechanism 3 comprises a stepping motor 301, an electromagnetic clutch 302 and an electromagnetic latch 303; a rotary change sensor 304 and a photoelectric coding sensor 305 are arranged on the safety rod driving mechanism 3, the rotary change sensor 304 is electrically connected with the rotary change angle acquisition module 203, and the photoelectric coding sensor 305 is electrically connected with the photoelectric coding acquisition module 204; the motor driving module 202 is electrically connected with the stepping motor 301; the electromagnetic card lock control circuit 205 is electrically connected with the electromagnetic card lock 303; the electromagnetic clutch control circuit 206 is electrically connected to the electromagnetic clutch 302; the electromagnetic clutch 302 and the electromagnetic card lock 303 are arranged on the output shaft of the safety rod driving mechanism 3; the output shaft of the stepping motor 301 is in transmission connection with the safety rod assembly 4 to drive the safety rod assembly 4 to rotate and drop rods.
In this embodiment, the industrial control computer 1, the control cabinet 2 and the safety rod driving mechanism 3 are sequentially connected through a split shielded cable. The distance between the control cabinet 2 and the safety rod driving mechanism 3 is 18-20 m, so that the personal safety of testing personnel is guaranteed. The industrial control computer 1 is an interactive interface between a tester and the system, and the tester realizes the performance test of the safety rod of the nuclear reactor through the industrial control computer 1. Firstly, the industrial control computer 1 controls the control cabinet 2 to drive the stepping motor 301 to rotate, and controls the electromagnetic clutch 302 to cut off and combine transmission, the electromagnetic latch 303 is used for braking the stepping motor 301, and the stepping motor 301, the electromagnetic clutch 302 and the electromagnetic latch 303 are matched together to control the rotation and the rotating speed of the safety rod assembly 4.
In the control cabinet 2, the UPS power module 201 serves as a power support for system operation, provides operating voltage for each module, and has power storage capability, so that normal voltage supply after a system is suddenly powered off can be realized, and a certain time is maintained to ensure normal storage of test data and reduce damage to equipment due to sudden power failure. Preferably, the UPS power module 201 in this embodiment is provided with a communication interface, and ethernet communication is established between the communication interface and the industrial control computer 1, so that power parameters of the UPS power module 201 can be acquired, and the electric quantity of the UPS power module 201 can be monitored. The motor drive module 202 provides kinetic energy for the operation of the safety bar assembly 4 and for the quick drop of the bar. The rotary variable angle acquisition module 203 is used for acquiring measurement data of the rotary variable sensor 304 to realize measurement of the rotation angle of the output shaft of the safety rod driving mechanism 3, and an acquisition result of the rotary variable angle acquisition module 203 is transmitted to the industrial control computer 1 to be operated and displayed, wherein the rotary variable sensor 304 can be realized by adopting a rotary transformer. The photoelectric encoding acquisition module 204 is used for acquiring the optical encoding value of the optical encoding sensor 204 and calculating the number of turns of the rotation of the output shaft of the safety rod driving mechanism 3.
Specifically, as shown in fig. 1, the system further includes an inflation/deflation assembly 5, and the inflation/deflation assembly 5 includes an inflation valve 501, an exhaust valve 502, and a pressure sensor 503, wherein: the control cabinet 2 further comprises an inflation and exhaust valve control circuit 207 and a pressure acquisition module 208, wherein the inflation and exhaust valve control circuit 207 is electrically connected with an inflation valve 501 and an exhaust valve 502; the pressure acquisition module 208 is electrically connected to the pressure sensor 503. The air charging and discharging assembly 5 is used for providing air pressure for the environment where the safety rod assembly 4 is located, the air charging valve 501 and the air discharging valve 502 are remotely controlled by the industrial personal computer 1 to adjust the air pressure of the environment where the safety rod is located, the pressure sensor 503 is used for measuring and feeding back the pressure, and the control accuracy of the industrial personal computer 1 can be further improved.
Specifically, as shown in fig. 1, the control cabinet 2 further includes a motor temperature acquisition module 209, the safety bar driving mechanism 3 further includes a temperature sensor 306 installed on the stepping motor 301, and the motor temperature acquisition module 209 is electrically connected to the temperature sensor 306. Temperature sensor 306 is used to measure the temperature on stepper motor 301, which may be achieved by a thermal resistance temperature sensor. The motor temperature acquisition module 209 is used for acquiring data measured by the temperature sensor 306. In this embodiment, the temperature sensor 306 may be installed at the coil inside the stepper motor 301, and the temperature is measured by a platinum resistance temperature sensor; the motor temperature acquisition module 209 provides six thermal resistance input channels, acquires the resistance of the platinum resistor and sends the resistance to the industrial control computer 1 for calculation.
Specifically, the control cabinet 2 further includes an electromagnetic card lock voltage and current collection module 210 and an electromagnetic clutch voltage and current collection module 211, the electromagnetic card lock voltage and current collection module 210 is electrically connected with the electromagnetic card lock 303, and the electromagnetic clutch voltage and current collection module 211 is electrically connected with the electromagnetic clutch 302. The electromagnetic card lock voltage and current acquisition module 210 and the electromagnetic clutch voltage and current acquisition module 211 respectively measure the working voltage and current of the electromagnetic card lock 303 and the electromagnetic clutch 302, and the industrial control computer 1 monitors the parameters in real time, so that whether the working states of the electromagnetic card lock 303 and the electromagnetic clutch 302 meet the requirements or not is judged at any time.
Specifically, the industrial control computer 1 includes a computer 101 and a data interface acquisition card 102, and the computer 101 is connected to the control cabinet 2 through the data interface acquisition card 102. Wherein: the computer 101 stores computer instructions, and the computer instructions are executed to process information collected by the rotation angle collection module 203, the photoelectric coding collection module 204, the pressure collection module 208, the motor temperature collection module 209, the electromagnetic lock voltage and current collection module 210, and the electromagnetic clutch voltage and current collection module 211, and send control signals to the motor drive module 202, the electromagnetic lock control circuit 205, the electromagnetic clutch control circuit 206, and the charging and discharging valve control circuit 207. The computer 101 finishes information acquisition and control command output of the system through the data interface acquisition card 102, simultaneously displays the processing result of the acquired information on a human-computer interaction interface established by a computer instruction, and testers operate the computer 101 to realize rotation control and rapid rod drop of the system, monitor the operating parameters of the system in real time and alarm the fault state in operation. The computer 101 of this embodiment controls the motor driving module 202, the electromagnetic lock control circuit 205, the electromagnetic clutch control circuit 206, and the charging/discharging valve control circuit 207, and then controls the states of the stepping motor 301, the electromagnetic clutch 302, and the electromagnetic lock 303, and at the same time, the rod falling time of the safety rod is calculated by the information collected by the rotation angle collection module 203 and the photoelectric encoding collection module 204, and the real-time monitoring of the state of the safety rod driving mechanism 3 is also realized by acquiring the relevant parameter information collected by the pressure collection module 208, the motor temperature collection module 209, the electromagnetic lock voltage/current collection module 210, and the electromagnetic clutch voltage/current collection module 211.
Specifically, the data interface acquisition card 102 in the embodiment of the present invention includes a PCI to serial port card 1021, an analog input card 1022, a digital output card 1023, and a motor drive card 1024, where: the PCI express port board 1021 is connected with the motor temperature acquisition module 209 and the rotation angle acquisition module 203, and the computer 101 acquires temperature information acquired by the motor temperature acquisition module 209 and rotation angle information acquired by the rotation angle acquisition module 203 through the PCI express port board 1021; the analog input board 1022 is connected to the pressure acquisition module 208, the electromagnetic lock voltage and current acquisition module 210, and the electromagnetic clutch voltage and current acquisition module 211, where the information input by the analog input board 1022 is analog information, including the pressure information acquired by the pressure acquisition module 208, and the voltage and current information acquired by the electromagnetic lock voltage and current acquisition module 210 and the electromagnetic clutch voltage and current acquisition module 211; the digital quantity output board card 1023 is connected with the electromagnetic card lock control circuit 205, the electromagnetic clutch control circuit 206 and the charging and discharging valve control circuit 207, sends digital quantity control commands to the electromagnetic card lock control circuit 205, the electromagnetic clutch control circuit 206 and the charging and discharging valve control circuit 207, controls the states of the electromagnetic card lock 303, the electromagnetic clutch 302, the charging valve 501 and the discharging valve 502, enables the electromagnetic card lock 303 to be attracted, held and released, enables the electromagnetic clutch 302 to be attracted and released, and enables the charging valve 501 and the discharging valve 502 to be opened and closed; the motor driving board 1024 is connected with the motor driving module 202 and the photoelectric code acquisition module 204, and the code value acquired by the photoelectric code acquisition module 204 is acquired through the motor driving board 1024, so that the displacement change of the safety rod assembly 3 is measured, a driving signal is output to the motor driving module 202, and the stepping motor 301 is driven to rotate. Meanwhile, the embodiment can also be configured with a multifunctional board card, and provide various interfaces such as AI, AO, DI, DO and the like for user function expansion.
Specifically, the electromagnetic clutch control circuit 206, the electromagnetic latch control circuit 205, and the charging and discharging valve control circuit 207 are all provided with magnetic latching relays. The industrial control computer 1 in this embodiment controls the on/off of the corresponding circuit by controlling the state of the magnetic latching relay in the corresponding circuit, and then controls the working states of the electromagnetic clutch 302, the electromagnetic latch 303, the inflation valve 501, and the exhaust valve 502.
The nuclear reactor safety rod performance testing system provided by the embodiment of the invention can safely and efficiently monitor the working performance of the safety rod assembly in various complex environments through the operation and operation of the industrial control computer, tests the rod falling time, is simple and convenient to operate, is safe and reliable, and is beneficial to ensuring the personal safety of testers; on the other hand, the system is the first time of industry in China for the performance test of the nuclear reactor safety rod, and has very high popularization value.
The above description is only a preferred embodiment of the present invention, and not intended to limit the scope of the present invention, and all modifications and equivalents of the present invention, which are made by the contents of the present specification and the accompanying drawings, or directly/indirectly applied to other related technical fields, are included in the scope of the present invention.
Claims (10)
1. A nuclear reactor safety rod performance test system, characterized in that, the system includes industrial control computer, control cabinet, safety rod actuating mechanism and safety rod subassembly, wherein: the industrial control computer is connected with the control cabinet;
the control cabinet comprises a UPS power supply module, and a motor driving module, a rotation angle acquisition module, a photoelectric coding acquisition module, an electromagnetic lock control circuit and an electromagnetic clutch control circuit which are respectively connected with the UPS power supply module;
the safety rod driving mechanism comprises a stepping motor, an electromagnetic clutch and an electromagnetic card lock; a rotary change sensor and a photoelectric coding sensor are mounted on an output shaft of the safety rod driving mechanism, the rotary change sensor is electrically connected with the rotary change angle acquisition module, and the photoelectric coding sensor is electrically connected with the photoelectric coding acquisition module; the motor driving module is electrically connected with the stepping motor; the electromagnetic card lock control circuit is electrically connected with the electromagnetic card lock; the electromagnetic clutch control circuit is electrically connected with the electromagnetic clutch; the electromagnetic clutch and the electromagnetic clamp lock are arranged on an output shaft of the safety rod driving mechanism; and the output shaft of the stepping motor is in transmission connection with the safety rod assembly.
2. The nuclear reactor safety rod performance testing system of claim 1, further comprising an inflation and exhaust assembly comprising an inflation valve, an exhaust valve, and a pressure sensor, wherein:
the control cabinet also comprises an inflation and exhaust valve control circuit and a pressure acquisition module, wherein the inflation and exhaust valve control circuit is electrically connected with the inflation valve and the exhaust valve; the pressure acquisition module is electrically connected with the pressure sensor.
3. The nuclear reactor safety rod performance testing system of claim 2, wherein the control cabinet further comprises a motor temperature acquisition module, the safety rod drive mechanism further comprising a temperature sensor mounted on the stepper motor, the motor temperature acquisition module being electrically connected to the temperature sensor.
4. The nuclear reactor safety rod performance testing system of claim 3, wherein the control cabinet further comprises an electromagnetic latch voltage current collection module and an electromagnetic clutch voltage current collection module, the electromagnetic latch voltage current collection module being electrically connected to the electromagnetic latch, the electromagnetic clutch voltage current collection module being electrically connected to the electromagnetic clutch.
5. The nuclear reactor safety rod performance testing system of claim 4, wherein the industrial control computer comprises a computer and a data interface acquisition card, the computer being connected to the control cabinet through the data interface acquisition card; wherein:
the computer storage has the computer instruction, operates the computer instruction is used for handling change angle collection module photoelectricity code collection module pressure collection module motor temperature collection module electromagnetic card lock voltage current collection module and electromagnetic clutch voltage current collection module's acquisition information, and to motor drive module electromagnetic card lock control circuit electromagnetic clutch control circuit the control signal is sent to the exhaust valve control circuit that fills.
6. The nuclear reactor safety rod performance testing system of claim 5, wherein the data interface acquisition card comprises a PCI to serial board, an analog input board, a digital output board, and a motor drive board, wherein:
the PCI serial port board card is connected with the motor temperature acquisition module and the rotation angle acquisition module;
the analog input board card is connected with the pressure acquisition module, the electromagnetic card lock voltage and current acquisition module and the electromagnetic clutch voltage and current acquisition module; the digital quantity output board card is connected with the electromagnetic card lock control circuit, the electromagnetic clutch control circuit and the charging and discharging valve control circuit; the motor drive board card is connected with the motor drive module and the photoelectric code acquisition module.
7. The nuclear reactor safety rod performance testing system of claim 6, wherein the electromagnetic clutch control circuit, the electromagnetic latch control circuit, and the charge and exhaust valve control circuit are each provided with a magnetic latching relay.
8. The system of claim 7, wherein the UPS power module is configured with a communication interface and is connected to the industrial computer via the communication interface.
9. The nuclear reactor safety rod performance testing system of claim 8, wherein the control cabinet is 18-20 m from the safety rod drive mechanism.
10. The nuclear reactor safety rod performance testing system of claim 9, wherein the industrial control computer, the control cabinet, and the safety rod driving mechanism are connected in sequence by a split shielded cable.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010925846.1A CN112102977A (en) | 2020-09-04 | 2020-09-04 | Nuclear reactor safety rod performance test system |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202010925846.1A CN112102977A (en) | 2020-09-04 | 2020-09-04 | Nuclear reactor safety rod performance test system |
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| CN202010925846.1A Pending CN112102977A (en) | 2020-09-04 | 2020-09-04 | Nuclear reactor safety rod performance test system |
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN106384611A (en) * | 2016-11-14 | 2017-02-08 | 广东核电合营有限公司 | Nuclear power station rod control system test device and method |
| CN110120269A (en) * | 2019-05-29 | 2019-08-13 | 中国核动力研究设计院 | One kind effectively eliminating the extended shutdown design method of nuclear power plant's reactor rod drop time |
| CN110955229A (en) * | 2019-12-04 | 2020-04-03 | 中国原子能科学研究院 | Comprehensive test platform for drum stick system |
| CN111599499A (en) * | 2020-04-17 | 2020-08-28 | 中国原子能科学研究院 | Method for measuring rod drop time of control rod driving mechanism |
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2020
- 2020-09-04 CN CN202010925846.1A patent/CN112102977A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106384611A (en) * | 2016-11-14 | 2017-02-08 | 广东核电合营有限公司 | Nuclear power station rod control system test device and method |
| CN110120269A (en) * | 2019-05-29 | 2019-08-13 | 中国核动力研究设计院 | One kind effectively eliminating the extended shutdown design method of nuclear power plant's reactor rod drop time |
| CN110955229A (en) * | 2019-12-04 | 2020-04-03 | 中国原子能科学研究院 | Comprehensive test platform for drum stick system |
| CN111599499A (en) * | 2020-04-17 | 2020-08-28 | 中国原子能科学研究院 | Method for measuring rod drop time of control rod driving mechanism |
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