CN211788198U - Nuclear power station test instrument system - Google Patents
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- CN211788198U CN211788198U CN202020322508.4U CN202020322508U CN211788198U CN 211788198 U CN211788198 U CN 211788198U CN 202020322508 U CN202020322508 U CN 202020322508U CN 211788198 U CN211788198 U CN 211788198U
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- 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
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Abstract
The utility model provides a nuclear power station test instrument system, the nuclear power station test instrument system comprises a measuring component, a signal acquisition and processing cabinet connected with the measuring component, a test operation platform connected with the signal acquisition and processing cabinet, and a gateway operation platform connected with the test operation platform, wherein the gateway operation platform is connected with a real-time information monitoring system; the measuring assemblies are arranged in the steam generator water supply flow control system, the main steam system and the steam generator sewage system. The embodiment of the utility model provides a can improve the security and the reliability of nuclear power station.
Description
Technical Field
The utility model relates to a nuclear power technology field especially relates to a nuclear power station test instrument system.
Background
A nuclear power plant refers to a facility that converts nuclear energy into electrical energy by appropriate means. Nuclear power plants replace the boilers of thermal power plants with nuclear reactors, and generate heat by the special form of "burning" of nuclear fuel in the nuclear reactors, so that the nuclear energy is converted into heat energy to heat water and generate steam. The construction and operation of nuclear power plants is a complex and high technology. Once the nuclear power plant sends an accident, serious consequences which are difficult to measure are brought. Therefore, automatic and periodic testing of nuclear power plant equipment is required to enable performance checking of the nuclear power plant equipment.
SUMMERY OF THE UTILITY MODEL
An embodiment of the utility model provides a nuclear power station test instrument system to solve and how to carry out automatic and periodic test's problem to nuclear power station equipment.
In order to solve the technical problem, the utility model discloses a realize like this:
in a first aspect, an embodiment of the present invention provides a nuclear power station test instrument system, which includes a measurement component, a signal acquisition and processing cabinet connected to the measurement component, a test operation platform connected to the signal acquisition and processing cabinet, and a gateway operation platform connected to the test operation platform, wherein the gateway operation platform is connected to a real-time information monitoring system;
the measuring assemblies are arranged in the steam generator water supply flow control system, the main steam system and the steam generator sewage system.
Optionally, the measurement assembly includes a temperature measurement subassembly, the temperature measurement subassembly includes a temperature sensor and a temperature transmitter connected to the temperature sensor, the temperature transmitter is connected to the signal acquisition and processing cabinet;
the measurement assembly further comprises a pressure measurement subassembly comprising a pressure transmitter connected with the signal acquisition and processing cabinet;
the measurement assembly further comprises a flow measurement subassembly comprising a flow transmitter connected with the signal acquisition and processing cabinet.
Optionally, the measurement assembly includes a first measurement assembly, and the measurement assembly further includes at least one of: a second measurement assembly, a third measurement assembly and a fourth measurement assembly;
the first measuring assembly is arranged in the steam generator feed water flow control system, the main steam system and the steam generator blowdown system respectively and is used for measuring signals used for a heat balance test;
the second measurement assembly is disposed within the reactor coolant system, the second measurement assembly for measuring a signal used to calculate core power;
the third measurement component is arranged in the nuclear instrument system and is used for measuring a power signal of the nuclear instrument system;
the fourth measuring component is arranged in the steam turbine regulating system and used for measuring an active power signal of the generator.
Optionally, the first measurement component is connected to the signal acquisition and processing cabinet through a first signal distribution module or a communication module of a distributed control system;
the second measuring component is connected with the signal acquisition and processing cabinet through a first grouping box;
the third measuring component is connected with the signal acquisition and processing cabinet through a second signal distribution module or a communication module of a nuclear instrument system;
and the fourth measuring component is connected with the signal acquisition and processing cabinet through a third signal distribution module or a communication module of an electric meter and fault recording system.
Optionally, the measurement assembly further comprises a fifth measurement assembly, and the fifth measurement assembly is a measurement assembly installed on site during testing;
the fifth measuring component is connected with a centralized grouping cabinet, and the centralized grouping cabinet is connected with the signal acquisition and processing cabinet.
Optionally, the fifth measurement assembly is connected to the centralized marshalling cabinet through a second marshalling box.
Optionally, the signal acquisition and processing cabinet, the test operation platform and the gateway operation platform are all arranged in a nuclear power station safety plant.
Optionally, the nuclear power plant test instrument system further includes a power distribution box, the power distribution box is connected to a power system, and the power distribution box is further connected to the signal acquisition and processing cabinet, the test operation platform, and the gateway operation platform, respectively;
the power distribution box is used for distributing two paths of power signals to the signal acquisition and processing cabinet.
Optionally, the test operation platform includes a data processing computer, and a printer, a display, a keyboard and a mouse respectively connected to the data processing computer.
Optionally, the gateway operating platform includes a gateway computer and a switcher connected to the gateway computer, and the switcher is connected to the display, the keyboard and the mouse respectively;
the data processing computer is respectively connected with the display, the keyboard and the mouse through the switcher.
In the embodiment of the utility model, the nuclear power station test instrument system comprises a measuring component, a signal acquisition and processing cabinet connected with the measuring component, a test operation platform connected with the signal acquisition and processing cabinet, and a gateway operation platform connected with the test operation platform, wherein the gateway operation platform is connected with a real-time information monitoring system; the measuring assemblies are arranged in the steam generator water supply flow control system, the main steam system and the steam generator sewage system. Therefore, the nuclear power plant equipment can be automatically and periodically tested by the nuclear power plant test instrument system, so that the safety and the reliability of the nuclear power plant can be improved.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings required to be used in the description of the embodiments of the present invention will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to these drawings without inventive labor.
Fig. 1 is a schematic structural diagram of a nuclear power plant test instrument system according to an embodiment of the present invention;
fig. 2 is a second schematic structural diagram of a nuclear power plant test instrument system according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, not all, of the embodiments of the present invention. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative efforts belong to the protection scope of the present invention.
Referring to fig. 1, fig. 1 is a schematic structural diagram of a nuclear power plant test instrument system provided in an embodiment of the present invention, and as shown in fig. 1, the nuclear power plant test instrument system includes a measurement component 11, a signal acquisition and processing cabinet 12 connected to the measurement component 11, a test operation platform 13 connected to the signal acquisition and processing cabinet 12, and a gateway operation platform 14 connected to the test operation platform 13, where the gateway operation platform 14 is connected to a real-time information monitoring system;
wherein, the measuring component 11 is arranged in the steam generator feed water flow control system, the main steam system and the steam generator blowdown system.
The signal acquisition and processing cabinet 12 may be configured to receive signals measured by the measurement component 11, for example, may be configured to receive measurement signals required for heat balance calculation, the measurement signals include pressure, flow, and temperature, and may supply power to the transmitter in the measurement component 11. The signal acquisition and processing cabinet 12 may be configured with a signal decoupling and isolation module, an analog signal acquisition module, a signal power supply module, acquisition software, a main control unit, a clock receiving module, and a network communication interface communicating with the test operating platform 13, the analog signal acquisition module may be used to implement isolation, a/D conversion, and the like, and the clock receiving module may be used to synchronize with a nuclear power station clock system.
In addition, the test operation platform 13 may be used for receiving the data collected by the signal collection and processing cabinet 12, and further processing and calculating, for example, calculating the reactor heat balance test. The gateway operating platform 14 may be configured to report data calculated by the test operating platform 13 to a real-time information monitoring system. The nuclear power plant test instrument system can be used for calculating the thermal balance test of the reactor power by arranging the measuring assembly 11 in the steam generator feed water flow control system, the main steam system and the steam generator blowdown system respectively. For example, the measuring components 11 can be arranged at the inlet and the outlet of the steam generator feed water flow control system, the inlet and the outlet of the main steam system, and the inlet and the outlet of the steam generator blowdown system, so that the parameters such as the temperature, the pressure and the flow of the secondary side inlet of the steam generator, the main steam pressure of the secondary side outlet of the steam generator, the blowdown flow of the steam generator and the like can be measured by the measuring components 11 and used for calculating the heat balance test of the reactor power.
It should be noted that the nuclear power plant test instrument system is not a conventional process and fluid system, and may be composed of field test instruments, such as a test component, a field instrument rack, a field grouping box, a distribution box for supplying power to the field grouping box, a centralized grouping cabinet, a signal acquisition and processing cabinet 12, a distribution box for supplying power to the signal acquisition and processing cabinet 12, a test operation platform 13, and the like, and is mainly used for a periodic performance test of a nuclear power plant. The measuring assembly 11 is arranged in the steam generator water supply flow control system, the main steam system and the steam generator sewage discharge system and can be used for a heat balance test of the unit. In addition, some measurement work can also be performed by marshalling boxes installed in the nuclear island plant.
Further, the support system of the nuclear power plant test instrument system may include the following systems: the system comprises a water supply flow control system, a steam generator blowdown flow system, a main steam system, a clock system, a nuclear island instrument power system, a nuclear island alternating current uninterrupted power system and a grounding system. The user system of the nuclear power plant test instrument system can comprise the following systems: the system comprises a feed water flow control system, a steam turbine adjusting system, a reactor coolant system, a nuclear instrument system, a main steam system and a real-time information monitoring system.
It should be noted that the plant test instrumentation system may be implemented to perform automatic and periodic tests throughout the operation of the plant to provide information on the performance of plant equipment or any possible deviation from certain specified parameters. The nuclear power plant test instrument system can be used for calculating the thermal balance test of the reactor power by arranging the measuring assembly 11 in the steam generator feed water flow control system, the main steam system and the steam generator blowdown system respectively. The cycle of the heat balance test can be generally once a week, and the heat balance test can be carried out at any time according to the requirements of operators. The nuclear power plant test instrument system can be a non-safety level system and is irrelevant to nuclear safety. The nuclear power plant test instrument system may not be required to be able to resist internal disasters in design, and thus, a defensive measure against the internal disasters may not be provided in the design process. In extreme environments, such as fire, pipe and vessel damage, etc., the nuclear power plant test instrumentation system may be rendered unusable.
Further, in design, the precision of a nuclear power plant test instrument system can be better than 1%, the system availability can be not lower than 99.99%, and the MTTR (Mean Time To Repair Time) can be lower than 1 hour. Under any test condition, the CPU load rate can be not more than 45%, the network load rate can be not more than 25%, and the load rate of the power module can be not more than 35%. To meet the expansion needs, the system spare may be as follows: the spare amount of the I/O module is not less than 25%, the slot of the cabinet module is not less than 25%, the spare amount of the terminal strip is not less than 25%, and the spare amount of various storages is not less than 50%. Non-metallic materials such as cables, terminals, wires and printed circuit boards in cabinets and operator stations, such as signal acquisition and processing cabinet 12, test operator station 13 and gateway operator station 14, may be characterized as low smoke, halogen free, flame retardant, non-toxic and corrosive products, preferably without the use of nylon and polyvinyl chloride materials. All cables except the optical cable meet the cable qualification requirements. All instrumentation cables except for optical cables, low voltage cables, may have shielding protection. When the nuclear power station test instrument system runs, the normal running of a related power supply system, a ventilation system, a lighting system, a fire detection system and the like can be maintained.
Additionally, the nuclear power plant test instrumentation system may be used for periodic tests, the life cycle of which may depend on the particular test. The nuclear power plant test instrument system can perform related tests at any set time. The nuclear power plant test instrument system can calculate and print test results of a thermal balance test and a periodic performance test of a pump/heat exchanger/filter. The nuclear power station test instrument system can combine objective conditions such as special nuclear safety requirements of a nuclear power station and maintenance requirements of the nuclear power station, effectively realize system functions, is a precondition and an important guarantee that the nuclear power station can operate efficiently and reliably, and can provide beneficial reference and reference for optimization of other related systems.
In practical application, when a hardware fault occurs in a nuclear power plant test instrument system, the hardware fault can be repaired as follows. And (3) maintenance of power supply failure: the 24V DC power supply that nuclear power station test instrument system part module adopted is dual supply configuration, and redundant power supply when power of the same kind breaks down, does not influence the normal operating of nuclear power station test instrument system, when power conversion module breaks down, under the condition of guaranteeing the normal work of system, can lift the wiring on the trouble power off, changes with spare parts. And (3) repairing the channel fault: when the acquisition channel fails, the wiring can be replaced on the standby channel under the assistance of operators, and under the condition that the overall operation of the nuclear power station is allowed, the program is modified on line, and the maintenance record is made. And (3) module fault maintenance: and under the condition that the overall operation of the nuclear power station is allowed, the standby equipment can be replaced under the assistance of operating personnel, and a maintenance record is made. And (3) fault maintenance of the controller: during overhaul, the nuclear power station test instrument system can be separated from field equipment, and spare parts can be replaced under the cooperation of operating personnel. And (3) fault maintenance of other equipment: the spare part can be replaced with the assistance of an operator. When a software fault occurs, the software fault can inform the operating personnel to find out the fault reason, solve the problem and download the program again.
It should be noted that, in order to ensure safe and reliable operation of the nuclear power plant test instrument system, periodic inspection can be performed. The following related periodic tests can generally be performed: after each operation period of the unit is finished, all the analog quantity acquisition board cards used are subjected to precision testing and calibration during the overhaul and material change of the unit. The channel test of the acquisition module can be carried out, and the precision test of all the used analog quantity signal acquisition modules can be carried out by utilizing the overhaul and material change period of the unit after each operation period of the unit is finished according to the design requirement. The channel calibration of the acquisition module can be carried out, the online calibration can be carried out, if the accuracy of the acquisition board cannot meet the requirement, the channel calibration can be carried out on the acquisition board, the offline calibration can also be carried out, for example, the calibration of a calibration table is carried out, and the accuracy calibration can be carried out on the module with out-of-tolerance accuracy and the calibration table can be utilized.
In the embodiment of the present invention, the nuclear power station test instrument system includes a measuring component 11, a signal collecting and processing cabinet 12 connected to the measuring component 11, a test operating platform 13 connected to the signal collecting and processing cabinet 12, and a gateway operating platform 14 connected to the test operating platform 13, wherein the gateway operating platform 14 is connected to a real-time information monitoring system; wherein, the measuring component 11 is respectively arranged in the steam generator feed water flow control system, the main steam system and the steam generator blowdown system. Therefore, the nuclear power plant equipment can be automatically and periodically tested by the nuclear power plant test instrument system, so that the safety and the reliability of the nuclear power plant can be improved.
Optionally, the measuring assembly 11 includes a temperature measuring subassembly, which includes a temperature sensor and a temperature transmitter connected to the temperature sensor, and the temperature transmitter is connected to the signal collecting and processing cabinet 12;
the measurement assembly 11 further comprises a pressure measurement subassembly comprising a pressure transmitter connected to the signal acquisition and processing cabinet 12;
the measurement assembly 11 also comprises a flow measurement subassembly comprising a flow transmitter connected to the signal acquisition and processing cabinet 12.
The temperature sensor can adopt a 4-wire Pt100 platinum resistance temperature sensor with A-level precision. The temperature transmitter can be a two-wire temperature transmitter which outputs 4 mA-20 mADC signals. The pressure transmitter can output 4 mA-20 mA DC signals, has a two-wire system, and has the precision superior to +/-0.01 percent. The flow transmitter can output 4 mA-20 mA DC signals, has a two-wire system, and has the precision superior to +/-0.01 percent.
The nuclear power plant test instrument system also comprises a dispersion instrument frame, a temperature sensor protection sleeve and an on-site power distribution box in the nuclear island plant, and the test assembly, the dispersion instrument frame, the temperature sensor protection sleeve and the on-site power distribution box in the nuclear island plant jointly form an on-site test network unit.
Optionally, the measurement assembly 11 includes a first measurement assembly, and the measurement assembly 11 further includes at least one of: a second measurement assembly, a third measurement assembly and a fourth measurement assembly;
the first measuring assembly is arranged in the steam generator feed water flow control system, the main steam system and the steam generator blowdown system respectively and is used for measuring signals used for a heat balance test;
the second measurement assembly is disposed within the reactor coolant system, the second measurement assembly for measuring a signal used to calculate core power;
the third measurement component is arranged in the nuclear instrument system and is used for measuring a power signal of the nuclear instrument system;
the fourth measuring component is arranged in the steam turbine regulating system and used for measuring an active power signal of the generator.
As shown in fig. 2, the first measurement assembly is used for measuring a signal x3 for a heat balance test, the second measurement assembly is used for measuring a signal x1 for calculating core power, the third measurement assembly is used for measuring a nuclear instrumentation system power signal x4, and the fourth measurement assembly is used for measuring a generator active power signal x 5.
Optionally, the first measurement component is connected to the signal acquisition and processing cabinet 12 through a first signal distribution module or a communication module of a distributed control system;
the second measuring assembly is connected with the signal acquisition and processing cabinet 12 through a first grouping box;
the third measuring component is connected with the signal acquisition and processing cabinet 12 through a second signal distribution module or a communication module of the nuclear instrument system;
the fourth measuring component is connected with the signal acquisition and processing cabinet 12 through a third signal distribution module or a communication module of an electricity meter and fault recording system.
As shown in fig. 2, the communication module of the Distributed Control System (DCS) may be a DCS a0 module, the communication module of the nuclear instrumentation system may be a nuclear instrumentation system a0 module, and the communication module of the electric meter and fault recording system may be an electric meter and fault recording system a0 module. The first signal distribution module, the second signal distribution module and the third signal distribution module can implement signal distribution transmission, for example, send the temperature measurement signal, the pressure measurement signal and the flow measurement signal to the signal acquisition and processing cabinet 12 in different channels.
Optionally, the measurement assembly 11 further includes a fifth measurement assembly, and the fifth measurement assembly is a measurement assembly installed on site during a test;
the fifth measurement component is connected to a centralized marshalling cabinet, which is connected to the signal acquisition and processing cabinet 12.
Wherein, the cabinet of organizing in concentration can be organized by binding post and organize, and the cabinet of organizing in concentration can be organized the case with the second and be connected, makes things convenient for the field debugging. The fifth measurement component may be used to measure a temporary test meter signal x 2.
Optionally, as shown in fig. 2, the fifth measurement component is connected to the centralized marshalling cabinet through a second marshalling box.
In order to facilitate periodic performance inspection of equipment such as pumps, heat exchangers and filters of a part of process systems during debugging and overhaul, a second marshalling box can be arranged on the site, and test point signals measured by a fifth measuring assembly temporarily installed on the site can include signals of a nuclear island and a conventional island and are transmitted to a centralized marshalling cabinet for centralized acquisition of signals through the second marshalling box installed on the site according to test or debugging requirements.
Optionally, the signal acquisition and processing cabinet 12, the test operation platform 13, and the gateway operation platform 14 are all disposed in a nuclear power plant safety building.
The power distribution box, the signal acquisition and processing cabinet 12, the centralized grouping cabinet, the test operation platform 13 and the gateway operation platform 14 can be used as a system centralized acquisition and processing unit and are arranged among instrument control electronic equipment of a safety factory building. The field test network unit formed by the test assembly, the dispersion instrument frame in the nuclear island plant, the temperature sensor protection sleeve and the field power distribution box can be dispersed and arranged in the nuclear island plant on the field.
Optionally, the nuclear power plant test instrument system further includes a power distribution box, the power distribution box is connected to a power system, and the power distribution box is further connected to the signal acquisition and processing cabinet 12, the test operation platform 13, and the gateway operation platform 14, respectively;
the power distribution box is configured to distribute two power signals to the signal acquisition and processing cabinet 12.
The nuclear Power station test instrument System can be powered by an Uninterruptible Power supply, can be powered by two 220V alternating current Power supplies in a redundant manner in a nuclear island, one path is provided with a UPS (Uninterruptible Power System), the other path is not provided with the UPS, and Power supply internal distribution of each cabinet and each operating platform can be carried out through a Power distribution box. The second marshalling box can be supplied with 220V alternating current power supply, and temporary standby power supply is provided for the site.
Optionally, as shown in fig. 2, the test operation platform 13 includes a data processing computer, a printer, a display, a keyboard, and a mouse, which are respectively connected to the data processing computer.
The test operation platform 13 may be configured to receive data collected by the signal collection and processing cabinet 12, and further process and calculate, for example, a reactor thermal balance test. The test operation platform 13 may further include a workbench with a color LCD, and may further include a hard disk large enough, where the hard disk may be used to store basic software and application software, temporary data before processing, test report forms, test constant tables, and the like. The printer may be a laser printer that prints the calculation result. The test operation platform 13 may further include a matching computing processing software and a network communication interface.
Optionally, as shown in fig. 2, the gateway operating platform 14 includes a gateway computer and a switch connected to the gateway computer, where the switch is connected to the display, the keyboard and the mouse, respectively;
the data processing computer is respectively connected with the display, the keyboard and the mouse through the switcher.
Wherein, the switch can realize that the display, the keyboard and the mouse are commonly used by the gateway operating platform 14 and the test operating platform 13. The gateway operating platform 14 may communicate with the real-time information monitoring system through a network interface configured thereto, and submit data and test calculation results acquired by the nuclear power plant test instrument system. The gateway operating platform 14 may also include a color LCD workstation, a hard disk for storing basic software and application software, temporary data before processing, test reports and test constants, and a network communication interface.
The embodiments in the present specification are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same and similar parts among the embodiments are referred to each other.
In the description of the present invention, it is to be understood that the terms "longitudinal", "radial", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", and the like indicate orientations or positional relationships based on those shown in the drawings, and are used merely for convenience of description and to simplify the description, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore should not be construed as limiting the present invention. In the description of the present invention, "a plurality" means two or more unless otherwise specified.
In the description of the present invention, it is to be noted that the terms "mounted", "disposed" and "connected" are to be construed broadly unless otherwise explicitly stated or limited. For example, the connection can be fixed, detachable or integrated; may be directly connected or indirectly connected through an intermediate. The fixed connection can be common technical schemes such as welding, threaded connection and clamping. The specific meaning of the above terms in the present invention can be understood in specific cases to those skilled in the art.
The above embodiments are only specific embodiments of the present invention, but the scope of the present invention is not limited thereto, and any person skilled in the art can easily think of changes or substitutions within the technical scope of the present invention, and all should be covered within the scope of the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (10)
1. A nuclear power station test instrument system is characterized by comprising a measuring component, a signal acquisition and processing cabinet connected with the measuring component, a test operation platform connected with the signal acquisition and processing cabinet, and a gateway operation platform connected with the test operation platform, wherein the gateway operation platform is connected with a real-time information monitoring system;
the measuring assemblies are arranged in the steam generator water supply flow control system, the main steam system and the steam generator sewage system.
2. The nuclear power plant test instrumentation system of claim 1, wherein the measurement assembly comprises a temperature measurement subassembly including a temperature sensor and a temperature transmitter coupled to the temperature sensor, the temperature transmitter coupled to the signal acquisition and processing cabinet;
the measurement assembly further comprises a pressure measurement subassembly comprising a pressure transmitter connected with the signal acquisition and processing cabinet;
the measurement assembly further comprises a flow measurement subassembly comprising a flow transmitter connected with the signal acquisition and processing cabinet.
3. The nuclear power plant test instrumentation system of claim 1, wherein the measurement assembly comprises a first measurement assembly, the measurement assembly further comprising at least one of: a second measurement assembly, a third measurement assembly and a fourth measurement assembly;
the first measuring assembly is arranged in the steam generator feed water flow control system, the main steam system and the steam generator blowdown system respectively and is used for measuring signals used for a heat balance test;
the second measurement assembly is disposed within the reactor coolant system, the second measurement assembly for measuring a signal used to calculate core power;
the third measurement component is arranged in the nuclear instrument system and is used for measuring a power signal of the nuclear instrument system;
the fourth measuring component is arranged in the steam turbine regulating system and used for measuring an active power signal of the generator.
4. The nuclear power plant test instrumentation system of claim 3, wherein the first measurement component is connected to the signal acquisition and processing cabinet via a first signal distribution module or a communication module of a distributed control system;
the second measuring component is connected with the signal acquisition and processing cabinet through a first grouping box;
the third measuring component is connected with the signal acquisition and processing cabinet through a second signal distribution module or a communication module of a nuclear instrument system;
and the fourth measuring component is connected with the signal acquisition and processing cabinet through a third signal distribution module or a communication module of an electric meter and fault recording system.
5. The nuclear power plant test instrumentation system of claim 1, wherein the measurement assembly further comprises a fifth measurement assembly, the fifth measurement assembly being a field-installed measurement assembly at the time of testing;
the fifth measuring component is connected with a centralized grouping cabinet, and the centralized grouping cabinet is connected with the signal acquisition and processing cabinet.
6. The nuclear power plant test instrumentation system of claim 5, wherein the fifth measurement component is connected to the centralized marshalling cabinet by a second marshalling box.
7. The nuclear power plant test instrumentation system of claim 1, wherein the signal acquisition and processing cabinet, the test operating platform, and the gateway operating platform are disposed within a nuclear power plant safety building.
8. The nuclear power plant test instrument system of claim 1, further comprising a power distribution box, the power distribution box being connected to a power system, the power distribution box being further connected to the signal acquisition and processing cabinet, the test operating platform, and the gateway operating platform, respectively;
the power distribution box is used for distributing two paths of power signals to the signal acquisition and processing cabinet.
9. The nuclear power plant test instrumentation system of claim 1, wherein the test operations platform comprises a data processing computer, a printer, a display, a keyboard, and a mouse respectively connected to the data processing computer.
10. The nuclear power plant test instrumentation system of claim 9, wherein the gateway operating platform comprises a gateway computer and a switch coupled to the gateway computer, the switch being coupled to the display, the keyboard, and the mouse, respectively;
the data processing computer is respectively connected with the display, the keyboard and the mouse through the switcher.
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| CN113409974A (en) * | 2020-03-16 | 2021-09-17 | 华龙国际核电技术有限公司 | A nuclear power plant test instrument system |
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