CN117594260A - Nuclear reactor process instrument simulation test system and method - Google Patents

Abstract

The invention discloses a nuclear reactor process instrument simulation test system and a method, wherein the simulation test system comprises a human-computer interface, is used for carrying out configuration design according to requirements and realizing measurement data, system working condition display and equipment operation control; the control system cabinet is linked with the human-computer interface to realize DCS operation environment simulation; the physical simulation cabinet comprises various measuring instruments, an actuating mechanism and power equipment and is used for simulating the operation working condition of the system according to the requirement. The invention is based on modularized design, adopts an integrated small-sized control system cabinet and is matched with a physical simulation cabinet, so that the DCS control system simulation and the process system operation environment simulation can be realized, the invention can be applied to the engineering site for verifying a large number of meters and measuring channels thereof, and the debugging and verification efficiency is improved; the function and performance verification of the DCS standby clamping piece can be realized, and meanwhile, the quick verification of the radioactive pollution instrument can be performed.

Description

Nuclear reactor process instrument simulation test system and method

Technical Field

The invention belongs to the technical field of nuclear reactor instrument control, and particularly relates to a nuclear reactor process instrument simulation test system and method.

Background

The research heap instrument control system needs to collect and process a large number of analog input AI signals, thermal resistance RTD signals, thermocouple TC signals, analog output AO signals, switching value input DI signals, switching value output DO signals, pulse input PI signals and other various measurement and control signals, and outputs the signals after being collected, monitored and transmitted by a sensor so as to realize the functions of display, recording, control, execution, alarm and the like, thus being the practical application of a comprehensive automatic control system.

The construction period of the research pile is longer, the debugging task is heavier, when the whole factory data acquisition and control system does not have working conditions, the existing means cannot carry out real-time communication on site, the batch process instruments are independent and scattered on the actual engineering site, the test content and the function which can be realized by the traditional test tool are relatively fixed and single, the simulation and the test of a large number of signals cannot be completed in a short time, and the debugging efficiency is relatively low.

The maintenance work after the daily maintenance of research heap signal monitoring instrument and trouble is more necessary and urgent, and after having experienced the long-term operation of taking the nuclear, numerous monitoring instruments expose to the radiation environment, have direct contact with the nuclear waste water that pollutes, and the outer inspection of going forward after inconvenient direct dismantlement is difficult, and the work of tracing to the source is comparatively difficult, if can't guarantee the accuracy of magnitude transmission, data acquisition and monitoring will lose meaning.

For the long-time storage of spare cards of the DCS in a warehouse, due to the specificity of an in-service system, the spare cards are required to be effective at any time, so that a set of safe and reliable system is also required to periodically check whether the functions and the performances of the spare cards are normal.

The research pile instrument control equipment has various types and complex signal transmission paths, and if a person has misoperation, the system equipment is damaged or personnel safety accidents are caused. Therefore, a training device with comprehensive training content, safety, reliability, convenience, flexibility and high cost performance is needed to be configured.

Disclosure of Invention

In order to solve the problem of radioactive instrument verification, a matched system lacks a control system or an effective standby DCS card fault diagnosis is carried out before the DCS is put into operation, the invention provides a nuclear reactor process instrument simulation test system and a nuclear reactor process instrument simulation test method.

The invention is realized by the following technical scheme:

a nuclear reactor process instrumentation simulation test system, the simulation test system comprising:

the human-computer interface is used for carrying out configuration design according to requirements and realizing measurement data, system working condition display and equipment operation control;

the control system cabinet comprises a signal acquisition and receiving module, a signal processing and control module, a network and communication module and is linked with the human-computer interface to realize DCS operation environment simulation;

and the physical simulation cabinet comprises various measuring instruments, an executing mechanism and power equipment and is used for simulating the operation working condition of the system according to the requirement.

The matched DCS system lacks a measurement and control system when not put into operation, a large number of meters and measurement channels of a research stack debugging site cannot be verified in a short time by adopting a traditional testing tool, and the debugging and verification efficiency is low; the radioactive substances are arranged on the watch strap of the in-service signal monitor of the research stack, so that the direct detection is inconvenient; the spare card of DCS needs to be effective at any time due to the specificity of the in-service system, and lacks effective verification means. Based on the above, the invention provides an integrated process instrument simulation test system, which is based on a modularized design, adopts an integrated small control system cabinet and is matched with a physical simulation cabinet, so that DCS control system simulation and process system operation environment simulation can be realized, and the integrated process instrument simulation test system can be applied to the engineering site for verifying a large number of instruments and measurement channels thereof, and the debugging and verification efficiency is improved; the function and performance verification of the DCS standby clamping piece can be realized, and meanwhile, the quick verification of the radioactive pollution instrument can be performed.

As a preferred embodiment, all I/O signals inside the control system cabinet of the present invention are integrated into the aviation plug on the side of the cabinet via an internal interconnect;

all signals in the physical simulation cabinet are collected through the transfer box and then connected to aviation plugs on the side face of the cabinet;

and the aviation plug on the side surface of the control system cabinet is connected with the aviation plug on the side surface of the physical simulation cabinet through a multi-core prefabricated cable. According to the invention, a large number of signal wires in the cabinets are integrated, and are connected externally through the aviation plug in a unified way, so that the data connection between the cabinets is simplified, and the installation and the disassembly are convenient.

As a preferred implementation mode, the control system cabinet and the human-computer interface of the invention carry out information interaction through a redundant process control network;

the redundant process control network comprises a switch, a network cable, a MODBUS-RTU and a MODBUS-TCP communication module.

As an optimal implementation mode, the bottoms of the control system cabinet and the physical simulation cabinet are provided with universal rollers, and the universal rollers have movable and lockable functions, so that the control system cabinet and the physical simulation cabinet can be quickly moved to an engineering site to perform simulation tests.

As a preferred implementation mode, the control system cabinet is externally connected with two paths of redundant power supplies, and the redundant power supplies are converted by the power supply conversion device and then supply power to all modules in the control system cabinet;

the control system cabinet is internally provided with a protective ground, a system ground and a shielding ground copper bar, and the copper bars are connected to corresponding grounding points through bus ground wires after classified summary, so that personal safety, control system safety and interference suppression are ensured;

all modules in the control system cabinet are solid-state circuits and all adopt standardized, modularized and plug-in structures, so that the testing and verification of channels, modules, cabinets and subsystems can be flexibly realized according to actual requirements. The invention has strong expandability and flexible operation through modularized design.

In the preferred embodiment, the control system cabinet of the invention also reserves an open third party system and equipment communication interface to realize the data interaction and test functions with the third party system and equipment.

As an optimal implementation mode, the physical simulation cabinet comprises a stainless steel water storage tank, a liquid level meter, an electromagnetic flowmeter, an intelligent regulating valve, a pump, an electric heater, a thermal resistor, a thermocouple, a differential pressure transmitter, a valve, a fan and an electric cabinet which are attached to a grid plate, wherein the equipment sequentially simulates and builds an operation condition scene;

wherein the measuring and control device is open above the grid plate and a signal interface is reserved.

In a second aspect, the invention provides a method for simulating a DCS control system based on the above-mentioned nuclear reactor process instrument simulation test system, the method comprising:

acquiring I/O point requirements, signal acquisition and transmission requirements and process system equipment control requirements of a matched system;

configuring corresponding hardware modules according to requirements;

performing hardware configuration: configuring parameters for each hardware module;

performing bit number configuration: configuring parameters for the bit numbers of various types of signal channels to be used;

performing functional block configuration: newly-built and edited functional blocks, and parameters and editing codes are added or set for the functional blocks; after compiling, storing the function blocks into a function block library, and subsequently calling the function blocks;

program configuration is carried out: newly creating an FBD user program, adding a functional block and a data reference at the same time, setting parameters of the functional block and reference bit numbers, and connecting the program block;

compiling and downloading configuration content;

and carrying out online debugging on the configuration content.

In a third aspect, the present invention provides a DCS fastener fault diagnosis method based on the above-mentioned nuclear reactor process instrument simulation test system, the DCS fastener fault diagnosis method comprising:

mounting a DCS clamping piece in a clamping groove corresponding to the control system cabinet;

starting the man-machine interface and the control system cabinet, simulating a DCS running environment, performing software and hardware configuration, and performing software program compiling and downloading;

if the downloading is successful, injecting corresponding analog signals through an external signal source, selecting five signal points of 0%, 25%, 50%, 75% and 100% in the full range for gradual increment test and five signal points of 100%, 75%, 50%, 25% and 1% for gradual decrement test, and judging whether the clamping piece is damaged, the precision and the response time meet the use requirements after testing each channel of the clamping piece one by one;

and (3) linking with the physical simulation cabinet, and performing continuous operation test for at least 72 hours to verify the reliability of long-term operation of the DCS card.

In a fourth aspect, the present invention exits a self-diagnostic method based on the nuclear reactor process instrumentation simulation test system described above, the self-diagnostic method comprising:

the operation information of each hardware module in the control system cabinet is monitored on line in real time, and fault information is recorded;

and analyzing step by step according to the alarm level, rapidly positioning the fault position of the equipment, and making a maintenance scheme.

In a fifth aspect, the present invention provides a method for verifying a radioactive contamination meter based on the above-mentioned nuclear reactor process meter simulation test system, the method for verifying a radioactive contamination meter comprising:

based on an analogy method, a system operation condition is built in the physical simulation cabinet, a radioactive contamination instrument is installed on a process instrument test bench in the physical simulation cabinet and is linked with the control system cabinet, so that whether the radioactive contamination instrument is damaged or not and whether a signal channel is unblocked or not is monitored on line, and whether the function of the radioactive contamination instrument is normal or not can be rapidly judged;

and the joint signal generating device is used for judging the full link precision from the measuring end to the display terminal.

As a preferred embodiment, the radiometer monitoring process of the present invention specifically comprises:

the method comprises the steps that a reflective contamination meter is installed to meter process management, radioactive isolation of a standard meter and a meter to be tested is achieved through backflushing isolation, and meter backflushing decontamination is carried out before the radioactive contamination meter is detected;

simulating the operation working condition of the system, and comparing the measurement data of the standard meter and the measurement data of the meter to be measured under the same operation working condition;

after the radioactive contamination instrument is verified, the radioactive contamination instrument is back flushed and decontaminated again, so that the radioactive instrument is guaranteed not to pollute a standard table, and the on-site verification of whether the function of the radioactive contamination instrument is normal is realized.

In a sixth aspect, the present invention provides a test training method based on the above-mentioned nuclear reactor process instrument simulation test system, where the test training method includes:

the equipment module in the physical simulation cabinet is matched with a standard instrument with higher precision, so that the static characteristic and dynamic characteristic comparison of the sensor can be carried out, and the instrument is used and calibrated;

or, performing various transmitter adjustment learning and use skill training;

or, system configuration software is utilized to carry out practical training on the signal acquisition, monitoring, transmission processing, display, recording, control, execution and alarm functions of each process system of the research stack;

or, through module combination training, single-loop open-loop and closed-loop control simulation can be realized, and the design and application training of a complex serial control system can be realized.

Compared with the prior art, the invention has the following advantages and beneficial effects:

1. the simulation test system provided by the invention adopts a modularized design and a movable design, can simulate the operation environment of the DCS and the process system according to actual needs, is convenient to move to an engineering site, can be applied to simulation and test of a large number of process instrument signals of which the research pile lacks a matched DCS control system, improves the debugging efficiency, effectively solves the problems that the research pile lacks a measurement and control system when the matched system DCS is not put into operation due to the shortage of the debugging period in the debugging process, has low debugging efficiency when the traditional test tool is used, and completes simulation and test of a large number of signals in a short time;

2. the simulation test system provided by the invention adopts a modularized design, can simulate the DCX running environment according to actual needs, and can carry out on-line rapid diagnosis on corresponding DCS clamping pieces, thereby effectively solving the problem that the existing DCS standby clamping pieces are not subjected to rapid and reliable diagnosis;

3. according to the simulation test system provided by the invention, the control system is linked with the physical simulation cabinet, based on an analogy method and combined with a corresponding instrument recoil process, so that the radioactive instrument is verified on line, the safety is ensured, the problem that the contaminated instrument cannot be verified and traced is solved, and the accuracy of magnitude transmission is ensured.

4. The simulation test system provided by the invention reserves an open communication interface of the third party system and the equipment, can realize information interaction with the third party system and the equipment, check test and the like, and has strong expandability.

5. The simulation test system provided by the invention can also be used as a practical training device for researching stack instrument control maintenance personnel with high efficiency, reliability and strong expansibility, and can effectively improve the working skills of operation and maintenance personnel.

Drawings

The accompanying drawings, which are included to provide a further understanding of embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiments of the invention. In the drawings:

FIG. 1 is a schematic diagram of a system principle architecture according to an embodiment of the present invention;

FIG. 2 is a simulation flow chart of a DCS control system according to an embodiment of the present invention;

FIG. 3 is a flow chart of a DCS card diagnostic process in accordance with an embodiment of the present invention;

FIG. 4 is a flow chart of a radioactive contamination meter calibration according to an embodiment of the present invention.

Detailed Description

Hereinafter, the terms "comprises" or "comprising" as may be used in various embodiments of the present invention indicate the presence of inventive functions, operations or elements, and are not limiting of the addition of one or more functions, operations or elements. Furthermore, as used in various embodiments of the invention, the terms "comprises," "comprising," and their cognate terms are intended to refer to a particular feature, number, step, operation, element, component, or combination of the foregoing, and should not be interpreted as first excluding the existence of or increasing likelihood of one or more other features, numbers, steps, operations, elements, components, or combinations of the foregoing.

In various embodiments of the invention, the expression "or" at least one of a or/and B "includes any or all combinations of the words listed simultaneously. For example, the expression "a or B" or "at least one of a or/and B" may include a, may include B or may include both a and B.

Expressions (such as "first", "second", etc.) used in the various embodiments of the invention may modify various constituent elements in the various embodiments, but the respective constituent elements may not be limited. For example, the above description does not limit the order and/or importance of the elements. The above description is only intended to distinguish one element from another element. For example, the first user device and the second user device indicate different user devices, although both are user devices. For example, a first element could be termed a second element, and, similarly, a second element could be termed a first element, without departing from the scope of various embodiments of the present invention.

It should be noted that: if it is described to "connect" one component element to another component element, a first component element may be directly connected to a second component element, and a third component element may be "connected" between the first and second component elements. Conversely, when one constituent element is "directly connected" to another constituent element, it is understood that there is no third constituent element between the first constituent element and the second constituent element.

The terminology used in the various embodiments of the invention is for the purpose of describing particular embodiments only and is not intended to be limiting of the various embodiments of the invention. As used herein, the singular is intended to include the plural as well, unless the context clearly indicates otherwise. Unless otherwise defined, all terms (including technical and scientific terms) used herein have the same meaning as commonly understood by one of ordinary skill in the art to which various embodiments of the invention belong. The terms (such as those defined in commonly used dictionaries) will be interpreted as having a meaning that is the same as the context of the relevant art and will not be interpreted in an idealized or overly formal sense unless expressly so defined herein in connection with the various embodiments of the invention.

For the purpose of making apparent the objects, technical solutions and advantages of the present invention, the present invention will be further described in detail with reference to the following examples and the accompanying drawings, wherein the exemplary embodiments of the present invention and the descriptions thereof are for illustrating the present invention only and are not to be construed as limiting the present invention.

Examples:

the test content and the function which can be realized by using the traditional test tool are relatively fixed and single, the simulation and the test of a large number of signals can not be completed in a short time, and the debugging efficiency is relatively low because the test period is short in the debugging process and the matched system DCS lacks a measurement and control system when the matched system is not put into operation; the radioactive substances are arranged on the watch strap of the in-service signal monitor of the research stack, so that the direct detection is inconvenient; the spare clamping piece of the DCS needs to be ensured to be effective at any time. In order to solve at least one of the above problems, the present embodiment proposes a nuclear reactor process instrumentation simulation test system.

As shown in fig. 1, the simulation test system provided in this embodiment mainly includes: control system cabinet, physical simulation cabinet, human-computer interface and connecting cable, etc. The control system cabinet mainly comprises a signal acquisition and receiving module (AI, DI, AO, DO and the like), a signal processing and control module (namely a main control module), a network and communication module (an Ethernet communication module, a serial port communication module and the like) and the like.

The control system cabinet receives two external redundant 220V alternating current power supplies, converts the two external redundant 220V alternating current power supplies into 24V direct current power supplies through the power supply conversion device and supplies power to equipment such as a main control module, an I/O module and a switch. The control system cabinet is internally provided with a protective ground, a system ground and a shielding ground copper bar, and the copper bars are connected to corresponding grounding points through bus ground wires after classified summary, so that personal safety is ensured, safety of the control system is ensured, and interference is suppressed. All modules in the control system cabinet are solid-state circuits, are in standardized, modularized and plug-in structures, and can flexibly test and verify channels, modules, cabinets and subsystems according to actual requirements. The control system cabinet is also reserved with an open third-party system and equipment communication interface, is provided with a serial communication module, an Ethernet communication module and a corresponding base, and can communicate with MODBUS-RTU and MODBUS-TCP protocol signals to realize data information interaction and test functions. The arrangement space and the I/O channel in the control system cabinet are sufficient in pre-quantity, and the integrity of various test measurement and control signal types can be ensured. The I/O signal outlet end inside the control system cabinet is arranged on the side surface of the cabinet through an aviation plug, and a low-smoke halogen-free flame-retardant wire or cable is used for wiring in the control system cabinet. The universal roller wheels (with movable and lockable functions) are attached to the bottom of the control system cabinet, so that the control system cabinet can be quickly moved to an engineering site to be quickly connected with the assembly, and the control system cabinet is not limited by sites, so that the convenience and the space applicability of the device are ensured.

The physical simulation cabinet mainly comprises various measuring instruments, controlled equipment and the like, can build various working conditions of a simulation process system, and specifically comprises, but is not limited to, equipment such as a stainless steel water storage tank, a liquid level meter, an electromagnetic flowmeter, an intelligent regulating valve, a pump, an electric heater, a thermal resistor, a thermocouple, a differential pressure transmitter, a valve, a fan, an electric cabinet and the like which are attached to a grid plate, and the equipment simulates a built operation working condition scene according to requirements. Wherein the measuring and control device is open above the grid plate and a signal interface is left. All signals of the instrument, the sensor, the actuating mechanism, the power equipment and the like are collected through the adapter box and then are connected into a quick plug (aviation plug). The universal roller wheels (with movable and lockable functions) are also attached to the bottom of the physical simulation cabinet, so that the physical simulation cabinet can be quickly moved to an engineering site to be quickly connected with the assembly, and the physical simulation cabinet is not limited by sites, so that the convenience and the space applicability of the device are ensured.

The embodiment adopts the multicore prefabricated cable to connect the physical simulation cabinet and the control system cabinet, so that the accurate butt joint of the signal loop can be realized, the reliability of the measurement and control channel is improved, and the rapid termination and disassembly of the signal can be realized.

The man-machine interface can be, but not limited to, a mobile notebook computer, and mainly realizes functions of measuring data, displaying system working conditions, controlling equipment operation and the like. The human-computer interface performs information interaction with the control system cabinet through a redundant process control network, wherein the redundant process control network consists of a switch, a network cable, a MODBUS-RTU, a MODBUS-TCP and other protocol signal communication modules, and functions of network communication, data transmission, third-party system information interaction and the like are realized.

Further, based on the simulation test system provided in the present embodiment, the simulation of the DCS control system may be implemented, as shown in fig. 2, and the specific process includes: firstly, acquiring I/O point demands of a matched DCS system, signal acquisition and transmission demands and process system equipment control demands; then corresponding hardware modules are configured for hardware configuration, and software configuration is carried out according to process logic, wherein the configuration content mainly comprises: (1) The hardware configuration is configuration parameters such as a main control module, a communication module, an I/O connection module, a test bench, an I/O module, an I/O channel and the like; (2) Bit number configuration, which configures parameters for bit numbers (analog-in AI, analog-out AO, analog-in DI, analog-out DO, standby channel) of various signal channels to be used; (3) User function block configuration is created and edited, parameters and editing codes are added/set for the user function block, the user function block configuration is saved to a function block library after compiling, and the function block can be called subsequently; (4) And (3) user program configuration, namely newly building an FBD user program, adding functional blocks and data references, setting parameters of the functional blocks and reference bit numbers, connecting the program blocks, and finally completing compiling and downloading configuration contents.

After the test procedure and the configuration of the flow chart are completed, the configuration content is required to be debugged. The debugging content mainly comprises: the control system cabinet is electrified, a configuration interface is opened, an online debugging mode is entered, signals are added to the IO base one by one, and the value of a relevant channel can be checked in a monitoring interface, so that whether the channel is normal, whether the measurement precision meets the requirement or not is determined. The alarm value of the bit number and whether the state is forced or not can be changed by adjusting the specific parameters of the bit number; parameter modification is performed in bit debugging, an input bit number is set to be mandatory, or a functional block is placed in a debugging file, and then the value of the bit number is manually input to cover various operation modes and control priorities of equipment, so that whether program logic meets expectations or not is verified. And comparing the output value after the equipment logical operation with an expected result, if the output value is consistent with the expected result, passing the output value, and if the output value is inconsistent with the expected result, not passing the output value. And after the test is finished, releasing the forced value and recovering to the initial state of the system.

Furthermore, based on the above simulation test system, fault diagnosis of the spare part of the DCS card can also be realized, as shown in fig. 3, and the diagnosis process specifically includes: installing a DCS clamping piece into a clamping groove corresponding to a system control cabinet, commissioning a control system (namely the control system cabinet and a human-computer interface), simulating a DCS running environment, performing software and hardware configuration, performing software program compiling and downloading, and performing online diagnosis on whether a DCS inter-bay fixed program runs normally or not, wherein the process is specifically like the simulation process of the DCS control system, and the simulation process is not repeated; corresponding analog signals are injected through an external signal source, five signal points of 0%, 25%, 50%, 75% and 100% in the full range are selected for gradual increment test, and five signal points of 100%, 75%, 50%, 25% and 1% are gradually decreased, and after each channel of the clamping piece is tested one by one, whether the clamping piece is damaged, and whether the precision and the response time meet the use requirements are judged. And finally, through linkage with the physical simulation device, carrying out a baking machine test for at least 72 hours to verify the reliability of long-term operation of the clamping piece.

The embodiment can realize the fault diagnosis of the clamping piece and the channel level, the simulation test system also has a self-diagnosis function, and can monitor the operation information of a redundant control network (network port state and IP information of each node), a main control module (operation state, CPU load, network port state, hardware information, configuration information, communication information, version information, bus communication state, type consistency detection and the like) on line in real time, record fault information, analyze step by step according to alarm types by test and maintenance personnel, quickly position equipment fault positions and make a maintenance scheme, thereby efficiently solving the problems.

Further, based on the above simulation test system, the verification of the radioactive contamination meter can be realized, as shown in fig. 4, and the verification process specifically includes: based on analogy, a thermodynamic parameter simulation operation environment such as temperature, liquid level, pressure, differential pressure and the like and a radioactive instrument recoil system are built in the physical simulation cabinet, instruments are installed on a process instrument test bench in the physical simulation cabinet and are linked with a control system cabinet, the control system cabinet simulates a DCS operation environment, the specific simulation process is described in the DCS simulation process, and details are omitted, so that whether the on-line monitoring instrument is damaged, a signal channel is smooth or not, and whether the instrument functions are normal or not can be rapidly judged; and further carrying out full-link precision judgment from the measuring end to the display terminal by combining the signal generating device.

Specifically, the embodiment adopts an instrument backflushing process, a standard meter is set based on an analogy method for comparison analysis, a radioactive instrument is installed to the instrument backflushing process for management, the radioactive isolation of the standard meter (the instrument in the physical simulation cabinet) and the to-be-detected meter (the radioactive contamination instrument) is realized through backflushing isolation, instrument backflushing decontamination is firstly carried out before the instrument is detected, the operation working condition of a system is then simulated, the measurement data of the standard meter and the to-be-detected meter under the same operation working condition are compared, and after the radioactive instrument is detected, instrument backflushing decontamination is carried out again, so that the radioactive instrument is guaranteed not to pollute the standard instrument, whether the function of the polluted instrument is normal or not is detected on site, the problem that the polluted instrument cannot be detected and traced is solved, and the accuracy of magnitude transmission is guaranteed.

Furthermore, the embodiment can also be interconnected with an external system (third party equipment) through a serial port communication module and an Ethernet communication module in the control system cabinet, so that the correctness test, the accuracy test and the logic reliability test can be realized on the signals of the third party system.

Furthermore, various modules and measuring instruments in the simulation test system provided by the embodiment are of independent and associated structures, so that single instrument practical training can be performed according to actual needs, and the simulation test can be performed by matching and combining the complex process system. Each edition has complete functions, can be flexibly configured, supplemented and deleted according to the simulation operation or personnel training requirements, and has extremely strong expansibility. Based on the simulation test system, at least the following test training can be completed:

(1) The equipment module in the physical simulation cabinet is matched with a standard instrument with higher precision, so that static characteristics and dynamic characteristics of sensors (such as a resistance sensor, a capacitance sensor, an inductance sensor, a magneto-electric/magneto-electric sensor, a thermoelectric sensor, an integrated intelligent sensor and the like) can be analyzed and compared, and the instrument is used and calibrated.

(2) Various transmitters can be used for adjustment and study and training of using skills, such as a common pressure/differential pressure transmitter, a temperature transmitter, a liquid level transmitter, a flow transmitter and the like; the action principle and characteristics of the actuator, such as an electric actuator, a pneumatic actuator and the like, are known.

(3) The system configuration software is utilized to perform practical operation training on the functions of signal acquisition, monitoring, transmission processing, display, recording, control, execution, alarm and the like of each process system of the research stack.

(4) Through module combination training, single-loop open-loop and closed-loop control simulation of temperature, pressure, flow, liquid level and the like can be realized, the design and application training of a complex serial control system are realized, and the parameter setting and control effect ratio of the PID controller are equal.

The foregoing description of the embodiments has been provided for the purpose of illustrating the general principles of the invention, and is not meant to limit the scope of the invention, but to limit the invention to the particular embodiments, and any modifications, equivalents, improvements, etc. that fall within the spirit and principles of the invention are intended to be included within the scope of the invention.

Claims (13)

1. A nuclear reactor process instrumentation simulation test system, the simulation test system comprising:

the human-computer interface is used for carrying out configuration design according to requirements and realizing measurement data, system working condition display and equipment operation control;

the control system cabinet comprises a signal acquisition and receiving module, a signal processing and control module, a network and communication module and is linked with the human-computer interface to realize DCS operation environment simulation;

and the physical simulation cabinet comprises various measuring instruments, an executing mechanism and power equipment and is used for simulating the operation working condition of the system according to the requirement.

2. The nuclear reactor process instrumentation simulation test system of claim 1, wherein all I/O signals inside the control system cabinet are integrated into the aviation plug on the side of the cabinet via an internal interconnect;

all signals in the physical simulation cabinet are collected through the transfer box and then connected to aviation plugs on the side face of the cabinet;

and the aviation plug on the side surface of the control system cabinet is connected with the aviation plug on the side surface of the physical simulation cabinet through a multi-core prefabricated cable.

3. The nuclear reactor process instrumentation simulation test system of claim 1, wherein the control system cabinet is in information interaction with the human-machine interface via a redundant process control network;

the redundant process control network comprises a switch, a network cable, a MODBUS-RTU and a MODBUS-TCP communication module.

4. The nuclear reactor process instrument simulation test system of claim 1, wherein the control system cabinet and the physical simulation cabinet are provided with universal rollers at the bottoms thereof, and the universal rollers have movable and lockable functions, so that the control system cabinet and the physical simulation cabinet can be quickly moved to an engineering site for simulation test.

5. The nuclear reactor process instrument simulation test system according to any one of claims 1-4, wherein the control system cabinet is externally connected with two paths of redundant power supplies, and each module in the control system cabinet is powered after being converted by a power conversion device;

the control system cabinet is internally provided with a protective ground, a system ground and a shielding ground copper bar, and the copper bars are connected to corresponding grounding points through bus ground wires after classified summary, so that personal safety, control system safety and interference suppression are ensured;

all modules in the control system cabinet are solid-state circuits and all adopt standardized, modularized and plug-in structures, so that the testing and verification of channels, modules, cabinets and subsystems can be flexibly realized according to actual requirements.

6. The nuclear reactor process instrument simulation test system of claim 5, wherein the control system cabinet further reserves an open third party system and equipment communication interface to enable data interaction and test functions with third party systems and equipment.

7. The nuclear reactor process instrument simulation test system of claim 1, wherein the physical simulation cabinet comprises a stainless steel water storage tank, a liquid level meter, an electromagnetic flowmeter, an intelligent regulating valve, a pump, an electric heater, a thermal resistor, a thermocouple, a differential pressure transmitter, a valve, a fan and an electric cabinet which are attached to a grid plate, and the devices simulate and build an operation condition scene in sequence;

wherein the measuring and control device is open above the grid plate and a signal interface is reserved.

8. A method of simulating a DCS control system based on a nuclear reactor process instrumentation simulation test system of any one of claims 1 to 7, the method comprising:

acquiring I/O point requirements, signal acquisition and transmission requirements and process system equipment control requirements of a matched system;

configuring corresponding hardware modules according to requirements;

performing hardware configuration: configuring parameters for each hardware module;

performing bit number configuration: configuring parameters for the bit numbers of various types of signal channels to be used;

performing functional block configuration: newly-built and edited functional blocks, and parameters and editing codes are added or set for the functional blocks; after compiling, storing the function blocks into a function block library, and subsequently calling the function blocks;

program configuration is carried out: newly creating an FBD user program, adding a functional block and a data reference at the same time, setting parameters of the functional block and reference bit numbers, and connecting the program block;

compiling and downloading configuration content;

and carrying out online debugging on the configuration content.

9. A method for diagnosing a DCS fastener failure based on a nuclear reactor process instrumentation simulation test system according to any one of claims 1 to 7, comprising:

mounting a DCS clamping piece in a clamping groove corresponding to the control system cabinet;

starting the man-machine interface and the control system cabinet, simulating a DCS running environment, performing software and hardware configuration, and performing software program compiling and downloading;

if the downloading is successful, injecting corresponding analog signals through an external signal source, selecting five signal points of 0%, 25%, 50%, 75% and 100% in the full range for gradual increment test and five signal points of 100%, 75%, 50%, 25% and 1% for gradual decrement test, and judging whether the clamping piece is damaged, the precision and the response time meet the use requirements after testing each channel of the clamping piece one by one;

and (3) linking with the physical simulation cabinet, and performing continuous operation test for at least 72 hours to verify the reliability of long-term operation of the DCS card.

10. A self-diagnostic method based on a nuclear reactor process instrumentation simulation test system according to any one of claims 1 to 7, wherein said self-diagnostic method comprises:

the operation information of each hardware module in the control system cabinet is monitored on line in real time, and fault information is recorded;

and analyzing step by step according to the alarm level, rapidly positioning the fault position of the equipment, and making a maintenance scheme.

11. A method of radioactive contamination meter verification based on a nuclear reactor process meter simulation test system as set forth in any one of claims 1-7, wherein the method of radioactive contamination meter verification comprises:

based on an analogy method, a system operation condition is built in the physical simulation cabinet, a radioactive contamination instrument is installed on a process instrument test bench in the physical simulation cabinet and is linked with the control system cabinet, so that whether the radioactive contamination instrument is damaged or not and whether a signal channel is unblocked or not is monitored on line, and whether the function of the radioactive contamination instrument is normal or not can be rapidly judged;

and the joint signal generating device is used for judging the full link precision from the measuring end to the display terminal.

12. The method of radiometer verification as defined in claim 11 wherein said radiometer monitoring process comprises:

the method comprises the steps that a reflective contamination meter is installed to meter process management, radioactive isolation of a standard meter and a meter to be tested is achieved through backflushing isolation, and meter backflushing decontamination is carried out before the radioactive contamination meter is detected;

simulating the operation working condition of the system, and comparing the measurement data of the standard meter and the measurement data of the meter to be measured under the same operation working condition;

after the radioactive contamination instrument is verified, the radioactive contamination instrument is back flushed and decontaminated again, so that the radioactive instrument is guaranteed not to pollute a standard table, and the on-site verification of whether the function of the radioactive contamination instrument is normal is realized.

13. A test training method based on a nuclear reactor process instrumentation simulation test system according to any one of claims 1 to 7, wherein the test training method comprises:

the equipment module in the physical simulation cabinet is matched with a standard instrument with higher precision, so that the static characteristic and dynamic characteristic comparison of the sensor can be carried out, and the instrument is used and calibrated;

or, performing various transmitter adjustment learning and use skill training;

or, system configuration software is utilized to carry out practical training on the signal acquisition, monitoring, transmission processing, display, recording, control, execution and alarm functions of each process system of the research stack;

or, through module combination training, single-loop open-loop and closed-loop control simulation can be realized, and the design and application training of a complex serial control system can be realized.