CN115346696B - Verification system and method for nuclear safety level reactor core cooling monitoring system - Google Patents
Verification system and method for nuclear safety level reactor core cooling monitoring system Download PDFInfo
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- 238000012544 monitoring process Methods 0.000 title claims abstract description 57
- 238000001816 cooling Methods 0.000 title claims abstract description 53
- 238000012795 verification Methods 0.000 title claims abstract description 50
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- 238000004088 simulation Methods 0.000 claims abstract description 35
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- 238000004891 communication Methods 0.000 claims description 9
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
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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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a verification system and a verification method for a nuclear safety level reactor core cooling monitoring system, wherein the system comprises a reactor core temperature simulation module, a reactor core cooling monitoring system and a reactor core temperature control module, wherein the reactor core temperature simulation module is used for simulating and outputting reactor core temperature state signals of a reactor under various working conditions to the reactor core cooling monitoring system; the water level change simulation module is used for simulating and outputting reactor core water level state signals of the reactor under various working conditions to the reactor core cooling monitoring system; the working condition signal simulation module is used for simulating and outputting working condition signals of the nuclear power plant to the reactor core cooling monitoring system so as to provide a verification environment; the acquisition module is used for acquiring output signals of the reactor core cooling monitoring system; and the diagnosis and verification module is used for storing and comparing and verifying the acquired signals. The invention integrates data acquisition and signal simulation, on one hand, the invention can rapidly monitor and verify the acquisition equipment or working condition signals, and on the other hand, can generate the signal to simulate the reactor core state and send the signal to the corresponding equipment for diagnosis and processing.
Description
Technical Field
The invention belongs to the technical field of nuclear safety level equipment, and particularly relates to a verification system and method for a nuclear safety level reactor core cooling monitoring system.
Background
The reactor Core Cooling Monitoring System (CCMS) is used as one of subsystems of a Hualong No. one reactor core measuring system, belongs to safety level equipment, is mainly used for monitoring the reactor core outlet temperature, provides basis for radial power distribution of the reactor core, and can also be used for monitoring the change trend of the reactor core temperature and providing temperature parameters for measuring the reactor pressure vessel water level when a water loss accident occurs in the reactor, so that the safe operation of the reactor is ensured.
The reactor core cooling monitoring system of the nuclear power plant belongs to safety equipment, and is subjected to complex design and verification, in this stage, reactor working condition signals need to be provided and the correctness of the system needs to be fully verified, an M310 reactor core measuring system (RIC) only relies on using discrete meters to carry out single-precision test on each channel of the reactor core measuring system, the equipment cannot be diagnosed and the reactor core state cannot be simulated rapidly, verification of the calculation function of the reactor core measuring system cannot be met, a large number of required instruments are needed, time and labor are wasted, and the design and manufacturing period is greatly prolonged.
Disclosure of Invention
The invention provides a verification system for a nuclear safety level reactor core cooling monitoring system, which aims to solve the problems that equipment cannot be diagnosed and reactor core state can not be simulated rapidly in the prior art, corresponding requirements can not be met and the like. The verification system integrates data acquisition and signal simulation, can rapidly monitor and verify the acquisition equipment or working condition signals on one hand, and can generate signal simulation reactor core states on the other hand, and send the signal simulation reactor core states to corresponding equipment for diagnosis and processing.
The invention is realized by the following technical scheme:
the verification system for the nuclear safety level reactor core cooling monitoring system comprises a reactor core temperature simulation module, a water level change simulation module, a working condition signal simulation module, an acquisition module and a diagnosis and verification module;
the reactor core temperature simulation module is used for simulating and outputting reactor core temperature state signals of the reactor under various working conditions to the reactor core cooling monitoring system;
the water level change simulation module is used for simulating and outputting reactor core water level state signals of the reactor under various working conditions to the reactor core cooling monitoring system;
the working condition signal simulation module is used for simulating and outputting working condition signals of the nuclear power plant to the reactor core cooling monitoring system so as to provide a verification environment;
the acquisition module is used for acquiring output signals of the reactor core cooling monitoring system;
the diagnosis and verification module is used for storing and comparing and verifying the acquired signals.
As a preferred embodiment, the core temperature simulation module of the present invention can output 30 reactor core thermocouple signals simultaneously, the output thermocouple signals being in the range of 0 to 50mV.
As a preferred embodiment, the reactor core temperature simulation module is designed in a mode of independently isolating each output signal, and each output signal is protected by a shielding cable.
As a preferred embodiment, the system of the present invention further comprises a D/A module;
the diagnosis and verification module controls the D/A module to output 0V-2.5V test signals, the output test signals are attenuated by 50 times through the reactor core temperature simulation module, 0-50 mV signals are generated, and 30 paths of thermocouple signals are respectively and independently output after driving.
As a preferred embodiment, the water level change simulation module simulates a 2-way reactor core water level detector through a plurality of thermocouple signals and cold end compensation resistance signals.
As a preferred embodiment, the nuclear power plant operating condition signals of the invention include a main loop pressure wide-range signal, a main loop pressure narrow-range signal, an atmospheric pressure signal in the containment vessel, and a wide-range loop hot-zone temperature signal.
As a preferred embodiment, the signals collected by the collection module of the present invention include 23 current analog signals and 19 switching value signals.
As a preferred embodiment, the diagnostic and verification module of the present invention is implemented based on an FPGA.
As a preferred embodiment, the system of the invention further comprises a man-machine interaction module;
the man-machine interaction module is used for displaying, analyzing and recording the acquired signals.
On the other hand, the invention provides a verification method for a nuclear safety level reactor core cooling monitoring system, which is realized based on the verification system and specifically comprises the following steps of:
communication verification is carried out, and if communication is successful, the verification is started;
sending an analog signal to a corresponding module of a detected reactor core cooling monitoring system, storing the recovery data in a data pool, comparing and judging the recovery data, and verifying a reactor core temperature measurement function;
sending an analog signal to a corresponding module of a detected reactor core cooling monitoring system, storing the recovery data in a data pool, comparing and judging the recovery data, and verifying the water level testing function of the pressure vessel;
sending an analog signal to a corresponding module of a detected reactor core cooling monitoring system, storing the recovery data in a data pool, comparing and judging the recovery data, and verifying the reactor core cooling monitoring function;
and collecting output signals of the detected reactor core cooling monitoring system, storing the output signals in a data pool, comparing and judging the collected data, and verifying the reactor core output detection function.
The invention has the following advantages and beneficial effects:
the invention can realize the collection, rapid diagnosis and automatic test verification of the output result of the reactor core cooling monitoring system, and can provide multiple paths of analog signals for the reactor core cooling monitoring system, such as reactor core temperature state, reactor water level change and nuclear power plant working condition signals, thereby improving the fixed test and verification efficiency of the reactor core cooling monitoring system, simplifying the existing complex test process, saving the research time and providing technology and data support for the research of the reactor core cooling monitoring system.
The invention overcomes the complex electromagnetic environment of the nuclear power plant, is suitable for complex field environment, has the characteristics of anti-interference, high temperature resistance, electromagnetic compatibility resistance and vibration resistance, meets the field construction condition, and is suitable for the full-period development of a reactor core measurement system.
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 system schematic block diagram of an embodiment of the present invention.
Fig. 2 is a schematic diagram of a thermocouple signal generating circuit according to an embodiment of the present invention.
FIG. 3 is a schematic diagram of a thermal resistance signal generating circuit according to an embodiment of the present invention.
Fig. 4 is a schematic diagram of a switching value output signal generation circuit according to an embodiment of the present invention.
Fig. 5 is a schematic diagram of a current signal generating circuit according to an embodiment of the present invention.
Fig. 6 is a schematic diagram of a switching value signal acquisition circuit according to an embodiment of the present invention.
Fig. 7 is a schematic diagram of a current signal acquisition circuit according to an embodiment of the invention.
Fig. 8 is a schematic diagram of a voltage signal acquisition circuit according to an embodiment of the invention.
FIG. 9 is a flow chart of a method according to an embodiment of the 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
In order to ensure that CCMS can run reliably and stably for a long time, the embodiment provides a verification system for a nuclear safety level reactor core cooling monitoring system, which mainly comprises a reactor core temperature simulation module, a water level change simulation module, a working condition signal simulation module, an acquisition module, a diagnosis and verification module and a man-machine interaction module, as shown in fig. 1.
The reactor core temperature simulation module can simulate the reactor core temperature state, can output 30 paths of reactor core thermocouple signals simultaneously, simulate the reactor core temperature change under various working conditions such as reactor start-up, reactor shutdown, power lifting, stable operation, rod falling, accident and the like, and provide verification for the reactor core temperature measurement function and the reactor core cooling monitoring function of the reactor core cooling monitoring system. The output thermocouple signal range is 0-50 mV, mV level signals are easy to interfere, in order to meet the complex electromagnetic environment of the power plant, each signal is designed in a way of independent isolation, and the signals are protected by special shielding cables.
The water level change simulation module can simulate the water level change of the reactor, simulate a 2-channel reactor core water level detector through multi-channel thermocouple signals and cold end compensation resistance signals, simulate the water level state in the reactor core pressure vessel under various working conditions such as reactor start-up, reactor shutdown, power lifting, stable operation, rod falling, accidents and the like, simultaneously receive an adjustable heating power supply provided by CCMS for the reactor core water level detector, simulate the power consumption of the water level detector through an internal high-power resistor, and provide verification for the reactor core pressure vessel water level measurement function and the reactor core cooling monitoring function of the reactor core cooling monitoring system.
The working condition signal simulation module can simulate the working condition signals of the nuclear power plant such as the main circuit pressure wide-range signal, the main circuit pressure narrow-range signal, the atmospheric pressure signal in the containment, the wide-range loop hot-zone temperature signal and the like, and provides a verification environment for the test object cooling monitoring system.
The acquisition module is used for acquiring 23 paths of signals (23 paths of 4-20 mA signals) such as the highest core temperature, the average core outlet temperature and the lowest supercooling margin, and 19 paths of alarm signals (19 paths of dry contact input) such as the water level state signals and the supercooling margin low alarm signals which are output after CCMS calculation and processing, comparing the signals with theoretical values, and verifying the calculation result and the output function of the CCMS.
The diagnosis and verification module provides test signals for the CCMS through simulating the core thermocouple, the core water level detector and other nuclear power plant working condition signals, and is communicated with the CCMS through a network to rapidly diagnose and locate the CCMS faults, and can call the test cases to automatically complete the test and verification of the CCMS system. The diagnostic and verification module is implemented based on an FPGA.
And the man-machine interaction module can display, analyze, record and the like the acquired signals.
The types and ranges of signals involved in the system of this embodiment are shown in table 1.
TABLE 1 Signal types and ranges
Further, the core temperature analog signal, that is, the 0-50 mV signal generating circuit in this embodiment is shown in fig. 2, the FPGA controls the 16-bit D/a to output the 0V-2.5V test signal, the output test signal is attenuated by 50 times by using the operational amplifier, that is, the 0-50 mV signal can be generated, after driving, 30 paths of temperature analog signals are respectively and independently output, that is, each path of temperature analog signal is generated by a separate circuit module, fig. 2 illustrates that one path of temperature analog signal is taken as an example, and the output port is RO-1.
Further, the resistance analog signal in this embodiment, that is, the Pt100 resistance signal generating circuit is shown in fig. 3, after the FPGA controls the 16-bit D/a to output 1V to 1.75V signal, the FPGA adopts the op-amp to follow to generate high output impedance, and generates a differential pressure at the cold end of the four-wire thermocouple, and the differential pressure is calibrated to be about 20mV to 35mV corresponding to the D/a output at 0 to 200 ℃. The 24 paths of Pt100 resistors can be output in parallel during simulation, and the same cold end compensation temperature is output, namely two paths of thermocouple signals are output by two circuit modules at the same time, and the output ports shown in figure 3 are PT100-12/PT100-24.
Furthermore, the switching value analog signal of the embodiment, namely the output of the dry contact is realized by adopting a miniature relay, the FPGA provides 3 paths of isolated TTL signals, and the 3 paths of isolated TTL signals are conducted through a triode to drive the high-reliability Sonchuan miniature relay to be opened and closed so as to generate the output signal of the dry contact, and the output port is RY1-COM/RY1-NO, as shown in figure 4.
Further, in the 4-20 mA current analog signal of the embodiment, the FPGA controls the 5 paths of 16-bit DACs to output 0-2.5V signals, and the 5 paths of current analog signals are independently output through the power amplifying circuit, and the output port is YCH0, as shown in FIG. 5.
Further, in the switching value signal input of the embodiment, a single-path switching value input signal implementation circuit is shown in fig. 6, an actual 19-path dry contact input signal adopts a common pull-up resistor, is connected with the I/O of the FPGA to read, and is fed back to the processor to verify and test, and the acquisition port is YX1, as shown in fig. 6.
Further, in this embodiment, after the 4-20 mA current signal is input and the analog signal is sampled by adopting a 250 Ω precision resistor which is grounded, the analog signal is differentially driven to enter a 32-option 1 switch, and after the a/D cycle acquisition is controlled by the FPGA, the analog signal is fed back to the processor for verification test, as shown in fig. 7.
Further, in the embodiment, a voltage signal of 0-10V is input, the sampling port is X29-1, a current signal is collected, the voltage signal is generated after 4 resistors are shunted and protected, the differential driving is carried out on a 32-selector switch, the FPGA controls the ADC chip to circularly collect, and then the feedback result is fed back to the processor to be processed, as shown in FIG. 8.
The verification system provided by the embodiment can be connected with the tested core cooling monitoring system through hard wires and communicates through RS485 so as to provide various analog signals for the tested core cooling monitoring system, collect various signals output by the tested core monitoring system, and compare the signals with theoretical values so as to verify and test the functions of the tested core monitoring system; meanwhile, the verification system provided by the embodiment can also compare the acquired signal with the output signal to judge the test precision.
The working process of the verification system proposed in this embodiment is shown in fig. 8, and includes:
firstly, whether communication is successful or not is determined, a handshake signal is sent to a communication module, the communication module sends a handshake instruction to a tested system and then reads back, so that the communication state is judged, and detection or test is carried out if communication is successful.
And sending 22 thermocouple signals and 22 resistance signals to corresponding modules of the tested system, storing the recovery data in a data pool, and comparing and judging the recovery data, wherein the step is realized by verifying the reactor core temperature measurement function.
And sending 8 thermocouple signals and 2 resistance signals to corresponding modules of the tested system, storing the recovery data in a data pool, and comparing and judging the recovery data, wherein the step is realized by verifying the water level testing function of the pressure vessel.
And sending 1 main loop pressure signal, 1 safe atmospheric pressure signal and 3 hot pipe section temperature signals to corresponding modules of the tested system, storing the recovery data in a data pool, and comparing and judging the recovery data, wherein the step is realized by verifying the reactor core cooling monitoring function.
And sending an instruction to a corresponding module of the tested system, collecting 23 paths of analog quantity signals and 19 paths of switch signals, storing the signals in a data pool, and comparing and judging collected data, wherein the step is realized by verifying the reactor core output detection function.
The functions of core temperature, pressure vessel water level, core cooling monitoring, core output and the like can be tested through the process, and the functional modules can be independently realized and are not interfered with each other, and can also be simultaneously performed.
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 (7)
1. The verification system for the nuclear safety level reactor core cooling monitoring system is characterized by comprising a reactor core temperature simulation module, a water level change simulation module, a working condition signal simulation module, an acquisition module and a diagnosis and verification module;
the reactor core temperature simulation module is used for simulating and outputting reactor core temperature state signals of the reactor under various working conditions to the reactor core cooling monitoring system;
the water level change simulation module is used for simulating and outputting reactor core water level state signals of the reactor under various working conditions to the reactor core cooling monitoring system;
the working condition signal simulation module is used for simulating and outputting working condition signals of the nuclear power plant to the reactor core cooling monitoring system so as to provide a verification environment;
the acquisition module is used for acquiring output signals of the reactor core cooling monitoring system;
the diagnosis and verification module is used for storing and comparing and verifying the acquired signals; the reactor core temperature simulation module can output 30 paths of reactor core thermocouple signals at the same time, and the output thermocouple signals range from 0mV to 50mV; the reactor core temperature simulation module is designed in a mode that each path of output signals are isolated independently, and each path of output signals are protected by a shielding cable; the device also comprises a D/A module;
the diagnosis and verification module controls the D/A module to output 0V-2.5V test signals, the output test signals are attenuated by 50 times through the reactor core temperature simulation module, 0-50 mV signals are generated, and 30 paths of thermocouple signals are respectively and independently output after driving.
2. The verification system for a nuclear safety level core cooling monitoring system of claim 1, wherein the water level change simulation module simulates a 2-way core water level detector via a multi-way thermocouple signal and a cold end compensation resistance signal.
3. The verification system for a nuclear safety level core cooling monitoring system of claim 1, wherein the nuclear power plant operating condition signals include a main loop pressure wide range signal, a main loop pressure narrow range signal, an in-containment atmospheric pressure signal, and a wide range loop hot leg temperature signal.
4. A verification system for a nuclear safety level core cooling monitoring system as set forth in any one of claims 1-3 wherein the signals collected by the collection module comprise 23 current analog signals and 19 switching value signals.
5. The verification system for a nuclear safety level core cooling monitoring system of any one of claims 1-3 wherein the diagnostic and verification module is implemented based on an FPGA.
6. The verification system for a nuclear safety level core cooling monitoring system of any one of claims 1-3, further comprising a human-machine interaction module;
the man-machine interaction module is used for displaying, analyzing and recording the acquired signals.
7. A verification method for a nuclear safety level core cooling monitoring system, characterized in that the method is implemented based on a verification system according to any one of claims 1-6, comprising in particular the steps of:
communication verification is carried out, and if communication is successful, the verification is started;
sending an analog signal to a corresponding module of a detected reactor core cooling monitoring system, storing the recovery data in a data pool, comparing and judging the recovery data, and verifying a reactor core temperature measurement function;
sending an analog signal to a corresponding module of a detected reactor core cooling monitoring system, storing the recovery data in a data pool, comparing and judging the recovery data, and verifying the water level testing function of the pressure vessel;
sending an analog signal to a corresponding module of a detected reactor core cooling monitoring system, storing the recovery data in a data pool, comparing and judging the recovery data, and verifying the reactor core cooling monitoring function;
and collecting output signals of the detected reactor core cooling monitoring system, storing the output signals in a data pool, comparing and judging the collected data, and verifying the reactor core output detection function.
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