CN108630330B - Pressurized water reactor nuclear power station instrument system detector test processing method, device and system - Google Patents
Pressurized water reactor nuclear power station instrument system detector test processing method, device and system Download PDFInfo
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Abstract
The invention is suitable for the technical field of a reactor control and protection system, and provides a test processing method, a device and a system for a pressurized water reactor nuclear power station instrument system detector, wherein the method comprises the following steps: acquiring index data of a detector; amplifying and conditioning the index data; carrying out operation processing on the amplified and conditioned index data to obtain test data; evaluating the performance of the detector based on the test data. By the invention, the technical problem that the performance of the detector cannot be tested and verified in advance is solved; the off-line copying of the detector for a certain time is realized, and the reliability of the quality and the performance of the detector is ensured.
Description
Technical Field
The invention belongs to the technical field of a reactor control and protection system, and particularly relates to a test processing method, a device and a system for an instrument system detector of a pressurized water reactor nuclear power station.
Background
With the development of nuclear power, the number of detectors used by a multi-base-earth-station nuclear instrument RPN system is greatly increased, but the quality of the current detector depends on the quality report of a manufacturer and the field-based neutron source test, so that the performance of the detector cannot be tested and verified in advance; when the RPN system detector is applied to the field and has a fault, the signal is abnormally fluctuated or the unit is processed in a state quitting mode. Detector equipment adopted by the RPN system belongs to strategic spare parts of a nuclear power station, the storage period is long, and the defects existing in the RPN system detector can not be identified in advance and the reliability can not be verified in advance in the prior art.
Disclosure of Invention
In view of this, embodiments of the present invention provide a method, an apparatus, and a system for testing and processing a detector of a pressurized water reactor nuclear power plant instrumentation system, so as to solve the problem in the prior art that the defects of an RPN system detector cannot be identified in advance and the reliability cannot be verified in advance.
The first aspect of the embodiment of the invention provides a test processing method for a detector of a pressurized water reactor nuclear power station instrument system, which comprises the following steps:
acquiring index data of a detector;
amplifying and conditioning the index data;
carrying out operation processing on the amplified and conditioned index data to obtain test data;
evaluating the performance of the detector based on the test data.
The second aspect of the embodiments of the present invention provides a device for testing and processing a detector of an instrumentation system of a pressurized water reactor nuclear power plant, including:
the data acquisition unit is used for acquiring index data of the detector;
the first data processing unit is used for amplifying and conditioning the index data;
the second data processing unit is used for carrying out operation processing on the amplified and conditioned index data to obtain test data;
and the performance evaluation unit is used for evaluating the performance of the detector according to the test data.
A third aspect of an embodiment of the present invention provides a detector test processing system, including: a memory, a processor and a computer program stored in the memory and executable on the processor, the processor implementing the steps of the above-described probe test processing method when executing the computer program.
A fourth aspect of embodiments of the present invention provides a computer-readable storage medium, which stores a computer program that, when executed by a processor, implements the steps of the above-described probe test processing method.
Compared with the prior art, the embodiment of the invention has the following beneficial effects: according to the embodiment of the invention, the index data of the detector is acquired, the index data is amplified, conditioned and operated to obtain the required test data, and the performance of the detector is evaluated and verified in advance according to the test data, so that the technical problem that the performance of the detector cannot be tested and verified in advance is solved; the off-line copying of the detector for a certain time is realized, the reliability of the quality and the performance of the detector is ensured, and the method has stronger usability and practicability.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.
FIG. 1 is a schematic flow chart of an implementation of a pressurized water reactor nuclear power plant instrumentation system detector test processing method according to an embodiment of the present invention;
FIG. 2 is a schematic diagram of a source range high plateau characteristic provided by an embodiment of the present invention;
FIG. 3 is a schematic diagram of a negative high-pressure curve for mid-range compensation provided by an embodiment of the present invention;
FIG. 4 is a schematic diagram of a high plateau characteristic of a mid-range detector provided by an embodiment of the present invention;
FIG. 5 is a schematic diagram of a discrimination threshold curve of a source range detector provided by an embodiment of the invention;
FIG. 6 is a schematic diagram illustrating a process for determining detector performance at a knee point of a discrimination threshold curve according to an embodiment of the present invention;
FIG. 7 is a schematic diagram of a detector test processing apparatus provided by an embodiment of the present invention;
FIG. 8 is a schematic diagram of a probe test processing system provided by an embodiment of the present invention.
Detailed Description
In the following description, for purposes of explanation and not limitation, specific details are set forth, such as particular system structures, techniques, etc. in order to provide a thorough understanding of the embodiments of the invention. It will be apparent, however, to one skilled in the art that the present invention may be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present invention with unnecessary detail.
It will be understood that the terms "comprises" and/or "comprising," when used in this specification and the appended claims, specify the presence of stated features, integers, steps, operations, elements, and/or components, but do not preclude the presence or addition of one or more other features, integers, steps, operations, elements, components, and/or groups thereof.
It is also to be understood that the terminology used in the description of the invention herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention. As used in the specification of the present invention and the appended claims, the singular forms "a," "an," and "the" are intended to include the plural forms as well, unless the context clearly indicates otherwise.
It should be further understood that the term "and/or" as used in this specification and the appended claims refers to and includes any and all possible combinations of one or more of the associated listed items.
In order to explain the technical means of the present invention, the following description will be given by way of specific examples.
Fig. 1 is a schematic diagram illustrating an implementation flow of a test processing method for a pressurized water reactor nuclear power plant instrumentation system detector, which is provided by an embodiment of the present invention, and can be applied to offline verification and copying of the pressurized water reactor nuclear power plant instrumentation system detector, to evaluate a detector spare part in advance, and to confirm the reliability of the detector quality; as shown in fig. 1, the method may include the steps of:
and S101, acquiring index data of the detector.
In the embodiment, the detector is arranged outside the pressurized water reactor, and measures the nuclear power and the nuclear power distribution by detecting and monitoring the average neutron flux and the distribution of the neutron flux rapidly and continuously; the detector comprises a source range detector, a middle range detector and a power range detector; the source range detector is a boron implantation proportional counter and can give out redundant low-pass measurement signals when a reactor is shut down and a power station is started initially; the middle range detector is a boron implantation compensation ionization chamber and can provide redundant neutron detection signals; the power range detector is a six-section gamma compensation ionization chamber, and can give four-way redundant six-section neutron current signals and total average neutron flux current signals.
The index data of the detector are a pulse signal and a current signal which are provided by the detector and represent neutron flux.
Further, the acquiring index data of the detector comprises:
collecting a pulse signal output by a source range detector;
and acquiring a current signal of the intermediate range detector or the power range detector.
In the embodiment, the source range detector can monitor the reactor core leakage neutron fluence rate of six orders of magnitude, so that 1-10 orders of magnitude can be realized6Acquiring a cps pulse signal; the middle range detector monitors reactor core leakage neutron fluence rate, the power range monitors power level, and the range of the current signal which can be collected is 10-11～10-3A。
And S102, amplifying and conditioning the index data.
In this embodiment, the acquired index data is subjected to signal processing, the source range detector and the intermediate range detector respectively use a proportional technology tube and a fission chamber, the pulse signal and the current signal are not beneficial to long-distance transmission and have poor anti-interference capability, the acquired pulse signal and the acquired current signal need to be amplified and conditioned, and a digital pulse signal and an analog signal need to be output.
Further, the amplifying and conditioning the index data comprises:
amplifying, shaping and discriminating the pulse signals;
and carrying out current-voltage I-V conversion and voltage amplification processing on the current signal.
In the embodiment, the pulse signal is amplified, and the amplifying circuit acquires the shielding treatment of the metal box with a special process, so that the interference of the circuit is reduced, and the authenticity of the pulse signal amplification is ensured; shaping the amplified pulse signal to make the shape of the pulse signal closer to the required shape; when the source range detector works in a low-power stage, the interference of gamma rays on neutron flux rate is large, the measurement of the neutron flux is influenced, a discrimination threshold processing method is needed, a reasonable discrimination threshold is set, gamma interference pulses lower than the voltage threshold are discriminated, and more accurate pulse signals are obtained. The middle range detector or the power range detector generates a small current signal after receiving the thermal neutron signal, converts the current signal into a voltage signal, linearly amplifies the voltage signal, and simultaneously adopts a special process to shield the amplifying circuit, so that the influence of circuit noise is reduced, the authenticity of signal amplification is ensured, and after conversion and amplification, each measuring gear can output a standard amplifying signal of 0-10V.
And step S103, performing operation processing on the amplified and conditioned index data to obtain test data.
In this embodiment, the performing the operation processing on the amplified and conditioned index data includes: calculating the counting rate of the source range detector, acquiring characteristic data of the source range detector plateau, controlling a source range discrimination threshold and high pressure, calculating current of the intermediate range detector, controlling the selection and switching of intermediate range gears, acquiring characteristic data of the intermediate range plateau, and controlling the high pressure and compensation high pressure of the intermediate range detector, so as to obtain test data required by the offline verification and copying of the detector.
Further, the operation processing is performed on the amplified and conditioned index data to obtain test data, and the method includes:
acquiring the counting rate of a pulse signal of a source range detector;
calculating plateau characteristic data and discrimination threshold data of the source range detector according to the counting rate and the bias voltage of the source range detector;
controlling the working high pressure of the source range detector according to the plateau characteristic data of the source range detector;
and adjusting the pulse discrimination value according to the discrimination threshold data of the source range.
In this embodiment, the pulse signal is proportional to the number of primary ionized ion pairs generated by incident particles, if the range of the particles is not long, the type, number and number of the particles can be detected, and the smaller pulses generated by β and gamma rays can be screened out under the cooperation of the screening circuit, so that the pulse signal of α particles is recorded, the pulse signal is amplified and shaped, then the counting rate of the pulse signal is calculated, and the counting rate of the pulse signal can be calculated by the conversion coefficient of 10-11A/cps (1cps means one count per second or a count rate of 1) converts the calculated count rate into a current.
In the embodiment, for a boron-coated proportional counter of a source range, a plateau characteristic curve and a discrimination threshold curve are mainly detected, and the counting rate is related to the quantity of charges collected by an electrode; acquiring a plateau characteristic curve and a discrimination threshold curve of the source range detector according to the counting rate and the source range detector bias voltage signal; under the conditions that the irradiation intensity of a radiation source is not changed and a discrimination threshold is not changed, a curve obtained according to the change of a counting rate along with the bias voltage of a source range detector is a plateau characteristic curve, as shown in a plateau characteristic curve schematic diagram of the change of the bias voltage along with the counting rate shown in fig. 2, when the bias voltage exceeds a certain value, the counting rate is rapidly increased, when the bias voltage continues to be increased, the counting rate is slightly increased along with the increase of the bias voltage, and an obvious plateau region B exists; in plateau region B, if the count rate still increases slightly with the increase of bias voltage, it shows that the plateau is sloped, and can become plateau slope.
In this embodiment, the operating high voltage of the source range detector can be determined from the plateau characteristic curve of the source range detector, and the operating voltage of the source range detector is selected at the front 1/3 of the plateau B according to the portion of the plateau B in the plateau characteristic curve in fig. 2, and can be determined to be 750V as shown in the figure.
In this embodiment, the discrimination threshold refers to an adjustable threshold voltage set in the source range measurement channel to eliminate spurious interference generated by gamma rays and noise pulses; the neutron flux and the bias voltage are maintained unchanged, the obtained relation curve between the counting rate of the source range detector and the discrimination threshold is a discrimination threshold curve, the discrimination value can be set according to the discrimination threshold curve, the setting control can be carried out through a potentiometer, and the input setting can be carried out through an operation panel of the signal processing part.
Further, the operation processing is performed on the amplified and conditioned index data to obtain test data, and the method further includes:
calculating a current signal of the intermediate range detector;
and controlling the switching of the intermediate range gear of the current amplifying circuit according to the calculated current signal.
In the embodiment, the neutron current generated by the intermediate range detector is amplified and shaped, and the magnitude of the current signal is calculated through a field programmable gate array FPGA processing platform; wherein the measurable current range is 10-11A～10- 3A, each gear can output a direct current voltage signal of 0-10V. The switching of the intermediate range amplification gear can be controlled through the operation processing of the output direct-current voltage signal.
Further, the operation processing is performed on the amplified and conditioned index data to obtain test data, and the method further includes:
acquiring a plateau characteristic curve and a negative high-voltage curve of the intermediate range detector according to the current signal and the high-voltage signal of the intermediate range detector;
and determining the compensation high voltage of the intermediate range detector according to the negative high voltage curve of the intermediate range detector.
In this embodiment, for the compensation ionization chamber with intermediate range, the ionization chamber works in the saturation region, the change curve of the bias voltage of the intermediate range detector along with the current signal is the plateau characteristic curve of the intermediate range detector, and the change curve of the amplitude of the negative high voltage along with the time is the negative high voltage curve. Determining the compensated negative high voltage of the middle range detector according to the negative high voltage curve, such as the middle range compensated negative high voltage curve diagram shown in fig. 3; the compensated negative high pressure is determined according to the time parameter Δ T and the source range count rate N in the figure, where T0 is the time (inflection point of the IRC curve) of the unit stack jump or subcritical point, T1 is the time when the power drop reaches the occurrence of the intermediate range channel P6, the difference between the two is Δ T1-T0, the compensated negative high pressure is determined by reading the source range count rate N when P6 is not present (i.e. when the source range is put into operation) on the curve, and according to the standard in table 1. In addition, the parameters Δ T and N are normalized to 10min < Δ T <40min and 5000C/S < N <20000C/S, respectively.
TABLE 1
It should be noted that if the compensation voltage of the intermediate range detector is too large, the intermediate range current drops too fast in the shutdown process, the 1/2 intermediate range neutron flux measurement value exceeds the fixed value P6 and occurs in a non-early stage, the source range is too high in technology during operation, and the risk of reactor jump exists; if the compensation voltage of the middle range detector is insufficient, the current generated by the gamma rays cannot be filtered, the current of the middle range is reduced too slowly, and P6 does not appear too late, so that the risk that the source range cannot be put into operation on time exists; thus, if one of the variables (Δ T or count rate N) exceeds the standard, the compensation voltage of the intermediate-range channel is adjusted according to table 1.
And step S104, evaluating the performance of the detector according to the test data.
In this embodiment, the test data includes a plateau characteristic curve of the source range detector, a discrimination threshold curve of the source range detector, and a plateau characteristic curve of the intermediate range detector; and evaluating the performance of the detector according to the curve related to the test data, wherein the performance of the detector comprises the sensitivity and the aging state of the probe head of the detector.
Further, the evaluating the performance of the detector according to the test data includes:
and judging whether the probe of the intermediate range detector needs to be replaced or not according to the plateau characteristic data of the intermediate range detector.
In the embodiment, the degradation degree of the intermediate range detector is judged through the plateau characteristic curve of the intermediate range detector, and whether the probe needs to be replaced is judged according to the degradation degree. The plateau characteristic curve of the mid-range detector, shown in FIG. 4, is at high voltage V1To V3Between which is a flat zone of the plateau characteristic curve, V0At a rated voltage VnA voltage value corresponding to 20% of the saturation current; in order to characterize the slope of the plateau characteristic, a parameter P is defined,
wherein, V0Representing the initial sensitivity, V, of the intermediate range detector0The higher the probe degradation. When the plateau characteristic curve is greatly deformed, or V0If the voltage is more than 70V, the degradation of the probe is indicated, and whether the probe is aged or not needs to be monitored through a saturation plateau characteristic curve every three months; if the plateau characteristic continues to deform, or V0If the voltage is more than 140V or P is more than 6 percent, the probe is replaced at the next reactor shutdown.
In addition, the plateau characteristic curves of the long ionization chamber with the power range and the compensation ionization chamber with the intermediate range are similar, but the judgment standard of the probe is different, if the plateau characteristic curve of the long ionization chamber with the power range is seriously deformed or V is V0Above 30V indicates that the probe has begun to degrade, thereby increasing the probe's aging testFrequency of measurements, e.g., analysis of plateau characteristic curves every three months; if the curve continues to deform or V0Greater than 60V or P greater than 1.5%, the probe is replaced the next time the reactor is shut down.
Further, the evaluating the performance of the detector according to the test data further includes:
and evaluating the aging state of the source range detector according to the discrimination threshold data.
In the embodiment of the invention, the discrimination threshold curve of the source range detector can sensitively reflect the change of the amplification factor of the gas in the detector and can be used as a basis for evaluating the aging state of the source range detector, the discrimination threshold curve of the source range detector shown in figure 5 is used for quantitatively marking the degradation of the flat area of the detector in order to track the aging trend of the detector, a parameter △ C is set,
△ C degradation, i.e., △ C greater than 60%, indicates a change in the detector gas amplification, further reflecting the aging of the detector.
For example, a flow chart of judging detector aging by using a discrimination threshold curve inflection point shown in FIG. 6 is provided, C represents the aging degree of a flat region of a discrimination threshold curve, n represents the scale value of a discrimination threshold potentiometer, whether the curve has the inflection point is judged according to the discrimination threshold curve inflection point, if the inflection point exists and is located before a discrimination value 3, whether the inflection point is located before a discrimination value 2 is judged, if the inflection point is located before the discrimination value 2 and △ C (discrimination value 2 to discrimination value 4) is less than 60%, the discrimination value is adjusted to 3, indicating that a source range channel and a probe are normal, if the inflection point is located before a discrimination value 2 and the inflection point is located before a discrimination value 3, if the inflection point is located before a discrimination value 2 and the inflection point is located not less than 60%, judging that the probe aging is judged by combining a high-pressure plateau characteristic curve, the probe needs to be replaced, and the discrimination threshold curve is obtained again, if the probe does not exist before a discrimination threshold curve ITB 3, if the inflection point is located before a discrimination threshold curve 2, the probe does not exist, the probe needs to be replaced, if the probe does not exist, the probe needs to be replaced, if the probe needs to be obtained again, if the discrimination threshold curve is located before a discrimination threshold curve, and the probe does not smaller than 60%, the probe does not exist, and the probe needs to obtain a new probe does not obtain a high-based on a discrimination threshold curve, if the probe does not obtain a discrimination threshold curve, if the probe does not exist, the probe does not obtain a discrimination threshold curve is obtained, and the probe does not exist, the probe does not obtain a discrimination threshold curve, if the probe does not obtain a probe, and the probe does not obtain a probe does not obtain.
Further, the test processing method for the instrument system detector of the pressurized water reactor nuclear power station further comprises the following steps: and testing or calibrating the signal processing assembly according to the test data.
In this embodiment, according to the acquired index data of the detector, the signal processing component may be calibrated remotely or tested locally through a test circuit built in the component of the data acquisition and processing part.
According to the embodiment, the index data of the detector is acquired, the index data is amplified, conditioned and operated to obtain the required test data, and the performance of the detector is evaluated and verified in advance according to the test data, so that the technical problem that the performance of the detector cannot be tested and verified in advance is solved; the off-line copying of the detector for a certain time is realized, and the reliability of the quality and the performance of the detector is ensured.
It should be noted that, within the technical scope of the present disclosure, other sequencing schemes that can be easily conceived by those skilled in the art should also be within the protection scope of the present disclosure, and detailed description is omitted here.
It should be understood that, the sequence numbers of the steps in the foregoing embodiments do not imply an execution sequence, and the execution sequence of each process should be determined by its function and inherent logic, and should not constitute any limitation to the implementation process of the embodiments of the present invention.
Fig. 7 is a schematic diagram of a detector testing processing device according to an embodiment of the present invention, and for convenience of description, only the relevant parts of the detector testing processing device according to the embodiment of the present invention are shown.
The test processing device for the instrument system detector of the pressurized water reactor nuclear power station comprises:
the data acquisition unit 71 is used for acquiring index data of the detector;
a first data processing unit 72 for amplifying and conditioning the index data;
the second data processing unit 73 is configured to perform arithmetic processing on the amplified and conditioned index data to obtain test data;
a performance evaluation unit 74 for evaluating the performance of the detector based on the test data.
Further, the data acquisition unit 71 includes:
the pulse signal acquisition module is used for acquiring a pulse signal output by the source range detector;
and the current signal acquisition module is used for acquiring current signals of the intermediate range detector or the power range detector.
Further, the first data processing unit 72 includes:
the pulse adjusting circuit is used for amplifying, shaping and discriminating the pulse signals;
and the current amplifying circuit is used for carrying out current-voltage I-V conversion and voltage amplification processing on the current signal.
Further, the second data processing unit 73 includes:
the field programmable gate array FPGA circuit is used for acquiring the counting rate of a pulse signal of the source range detector and acquiring a plateau characteristic curve and a discrimination threshold curve of the source range detector according to the counting rate and the bias voltage of the source range detector; and the device is also used for calculating a current signal of the intermediate range detector and acquiring a plateau characteristic curve and a negative high-voltage curve of the intermediate range detector according to the current signal and the high-voltage signal of the intermediate range detector.
According to the embodiment, the index data of the detector is acquired, the index data is amplified, conditioned and operated to obtain the required test data, and the performance of the detector is evaluated and verified in advance according to the test data, so that the technical problem that the performance of the detector cannot be tested and verified in advance is solved; the off-line copying of the detector for a certain time is realized, and the reliability of the quality and the performance of the detector is ensured.
It will be apparent to those skilled in the art that, for convenience and simplicity of description, the foregoing division of the functional modules is merely illustrated, and in practical applications, the above function distribution may be performed by different functional units and modules as needed, that is, the internal structure of the mobile terminal is divided into different functional units or modules to perform all or part of the above described functions. Each functional module in the embodiments may be integrated in one processing unit, or each unit may exist alone physically, or two or more units are integrated in one unit, and the integrated unit may be implemented in a form of hardware, or in a form of software functional unit. In addition, specific names of the functional modules are only used for distinguishing one functional module from another, and are not used for limiting the protection scope of the application. The specific working process of the module in the mobile terminal may refer to the corresponding process in the foregoing method embodiment, and is not described herein again.
Fig. 8 is a schematic diagram of a probe test processing system according to an embodiment of the present invention. As shown in fig. 8, the probe test processing system 8 of this embodiment includes: a processor 80, a memory 81 and a computer program 82 stored in said memory 81 and executable on said processor 80. The processor 80, when executing the computer program 82, implements the steps of the various pressurized water reactor nuclear power plant instrumentation probe test processing method embodiments described above, such as the steps 101 through 104 shown in FIG. 1. Alternatively, the processor 80, when executing the computer program 82, implements the functions of the modules/units in the above-described device embodiments, such as the functions of the modules 71 to 74 shown in fig. 7.
Illustratively, the computer program 82 may be partitioned into one or more modules/units that are stored in the memory 81 and executed by the processor 80 to implement the present invention. The one or more modules/units may be a series of computer program instruction segments capable of performing specific functions that describe the execution of the computer program 82 in the probe trial processing system 8.
The detector test processing system 8 may include, but is not limited to, a processor 80, a memory 81. Those skilled in the art will appreciate that FIG. 8 is merely an example of the probe test processing system 8 and does not constitute a limitation of the probe test processing system 8, and may include more or fewer components than those shown, or some components may be combined, or different components, for example, the probe test processing system 8 may also include input and output devices, network access devices, buses, etc.
The Processor 80 may be a Central Processing Unit (CPU), other general purpose Processor, a Digital Signal Processor (DSP), an Application Specific Integrated Circuit (ASIC), a Field-Programmable Gate Array (FPGA) or other Programmable logic device, discrete Gate or transistor logic device, discrete hardware component, or the like. A general purpose processor may be a microprocessor or the processor may be any conventional processor or the like.
The memory 81 may be an internal storage unit of the probe test processing system 8, such as a hard disk or a memory of the probe test processing system 8. The memory 81 may also be an external storage device of the probe test processing system 8, such as a plug-in hard disk, a Smart Media Card (SMC), a Secure Digital (SD) Card, a Flash memory Card (Flash Card), or the like, provided on the probe test processing system 8. Further, the memory 81 may also include both an internal memory unit and an external memory device of the probe test processing system 8. The memory 81 is used to store the computer program and other programs and data required by the detector assay processing system 8. The memory 81 may also be used to temporarily store data that has been output or is to be output.
It will be apparent to those skilled in the art that, for convenience and brevity of description, only the above-mentioned division of the functional units and modules is illustrated, and in practical applications, the above-mentioned function distribution may be performed by different functional units and modules according to needs, that is, the internal structure of the apparatus is divided into different functional units or modules to perform all or part of the above-mentioned functions. Each functional unit and module in the embodiments may be integrated in one processing unit, or each unit may exist alone physically, or two or more units are integrated in one unit, and the integrated unit may be implemented in a form of hardware, or in a form of software functional unit. In addition, specific names of the functional units and modules are only for convenience of distinguishing from each other, and are not used for limiting the protection scope of the present invention. The specific working processes of the units and modules in the system may refer to the corresponding processes in the foregoing method embodiments, and are not described herein again.
In the above embodiments, the descriptions of the respective embodiments have respective emphasis, and reference may be made to the related descriptions of other embodiments for parts that are not described or illustrated in a certain embodiment.
Those of ordinary skill in the art will appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware or combinations of computer software and electronic hardware. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the implementation. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present invention.
In the embodiments provided in the present invention, it should be understood that the disclosed apparatus/terminal device and method may be implemented in other ways. For example, the above-described embodiments of the apparatus/terminal device are merely illustrative, and for example, the division of the modules or units is only one logical division, and there may be other divisions when actually implemented, for example, a plurality of units or components may be combined or integrated into another system, or some features may be omitted, or not executed. In addition, the shown or discussed mutual coupling or direct coupling or communication connection may be an indirect coupling or communication connection through some interfaces, devices or units, and may be in an electrical, mechanical or other form.
The units described as separate parts may or may not be physically separate, and parts displayed as units may or may not be physical units, may be located in one place, or may be distributed on a plurality of network units. Some or all of the units can be selected according to actual needs to achieve the purpose of the solution of the embodiment.
In addition, functional units in the embodiments of the present invention may be integrated into one processing unit, or each unit may exist alone physically, or two or more units are integrated into one unit. The integrated unit can be realized in a form of hardware, and can also be realized in a form of a software functional unit.
The integrated modules/units, if implemented in the form of software functional units and sold or used as separate products, may be stored in a computer readable storage medium. Based on such understanding, all or part of the flow of the method according to the embodiments of the present invention may also be implemented by a computer program, which may be stored in a computer-readable storage medium, and when the computer program is executed by a processor, the steps of the method embodiments may be implemented. Wherein the computer program comprises computer program code, which may be in the form of source code, object code, an executable file or some intermediate form, etc. The computer-readable medium may include: any entity or device capable of carrying the computer program code, recording medium, usb disk, removable hard disk, magnetic disk, optical disk, computer Memory, Read-Only Memory (ROM), Random Access Memory (RAM), electrical carrier wave signals, telecommunications signals, software distribution medium, and the like. It should be noted that the computer readable medium may contain other components which may be suitably increased or decreased as required by legislation and patent practice in jurisdictions, for example, in some jurisdictions, computer readable media which may not include electrical carrier signals and telecommunications signals in accordance with legislation and patent practice.
The above-mentioned embodiments are only used for illustrating the technical solutions of the present invention, and not for limiting the same; although the present invention has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not substantially depart from the spirit and scope of the embodiments of the present invention, and are intended to be included within the scope of the present invention.
Claims (14)
1. The test processing method of the instrument system detector of the pressurized water reactor nuclear power station is characterized by comprising the following steps:
acquiring index data of a detector;
amplifying and conditioning the index data;
carrying out operation processing on the amplified and conditioned index data to obtain test data;
evaluating the performance of the detector according to the test data; acquiring the counting rate of a pulse signal of a source range detector; calculating plateau characteristic data and discrimination threshold data of the source range detector according to the counting rate and the bias voltage of the source range detector; under the condition that the irradiation intensity of a radiation source is not changed and the discrimination threshold is not changed, a plateau characteristic curve corresponding to plateau characteristic data is obtained according to the change of the counting rate along with the bias voltage of the source range detector; keeping the neutron flux and the bias voltage unchanged, obtaining a relation curve between the counting rate of the source range detector and discrimination threshold data, discriminating a threshold curve, taking the discrimination threshold curve as a basis for evaluating the aging state of the source range detector, and tracking the aging trend of the detector;
based on a discrimination threshold curve of a source range detector, quantitatively identifying degradation of a detector flat area, and setting quantitative identification parameters; judging whether an inflection point exists in the curve according to a discrimination threshold curve, if the inflection point exists and is positioned before a discrimination value 3, judging whether the inflection point is positioned before a discrimination value 2, if the inflection point is positioned before the discrimination value 2, and the discrimination value 2 to 4 and the quantitative identification parameter are less than 60%, adjusting the discrimination value to be 3, and indicating that a source range channel and a probe are normal; if the inflection point is in front of the discrimination value 2, the discrimination value is from 2 to 4, and the quantitative identification parameter is not less than 60%, judging that the probe is aged by combining the high-pressure plateau characteristic curve, needing to replace the probe, and obtaining the discrimination threshold curve again; if the inflection point is before 3 and not before 2, the discrimination value is 3-5, and the quantitative identification parameter is not less than 60%, judging that the probe is aged by combining the high-voltage plateau characteristic curve, needing to replace the probe, and obtaining the discrimination threshold curve again; if the inflection point is not before 2 before 3, the discrimination value is 3-5, and the quantitative identification parameter is less than 60%, adjusting the discrimination value to be 4, and periodically checking the source range measurement channel under the condition that the drift of the source range measurement channel is acceptable; if the curve has no inflection point, the discrimination value is 2-4, and the quantitative identification parameter is not less than 60%, judging that the probe is aged by combining the high-pressure plateau characteristic curve, the probe needs to be replaced, and obtaining the discrimination threshold curve again; if the curve has no inflection point, the discrimination value is 2-4, and the quantitative identification parameter is less than 60%, adjusting the discrimination value to 3, and periodically checking the measurement channel under the condition that the drift of the measurement channel is acceptable;
wherein the discrimination value is a scale value representing a discrimination threshold potentiometer.
2. The method for testing and processing the detector of the instrument system of the pressurized water reactor nuclear power station as claimed in claim 1, wherein the step of collecting the index data of the detector comprises the steps of:
collecting a pulse signal output by a source range detector;
and acquiring a current signal of the intermediate range detector or the power range detector.
3. The PWR nuclear power plant instrumentation system probe test processing method of claim 2, wherein the amplifying and conditioning the indicator data comprises:
amplifying, shaping and discriminating the pulse signals;
and carrying out current-voltage I-V conversion and voltage amplification processing on the current signal.
4. The method for testing and processing the detector of the instrument system of the pressurized water reactor nuclear power station as claimed in claim 2, wherein the step of performing operation processing on the amplified and conditioned index data to obtain test data comprises the following steps:
and determining the working high pressure of the source range detector according to the plateau characteristic curve of the source range detector.
5. The method for testing and processing the detector of the instrument system of the pressurized water reactor nuclear power station as claimed in claim 2, wherein the step of performing operation processing on the amplified and conditioned index data to obtain test data further comprises the steps of:
calculating a current signal of the intermediate range detector;
and controlling the switching of the intermediate range gear of the current amplifying circuit according to the calculated current signal.
6. The method for testing and processing the detector of the instrument system of the pressurized water reactor nuclear power station as claimed in claim 5, wherein the operation processing is performed on the amplified and conditioned index data to obtain test data, further comprising:
acquiring a plateau characteristic curve and a negative high-voltage curve of the intermediate range detector according to the current signal and the high-voltage signal of the intermediate range detector;
and determining the compensation negative high voltage of the intermediate range detector according to the negative high voltage curve of the intermediate range detector.
7. The PWR nuclear power plant instrumentation probe test processing method of claim 6, wherein the evaluating the performance of the probe based on the test data comprises:
and judging whether the probe of the intermediate range detector needs to be replaced or not according to the plateau characteristic data of the intermediate range detector.
8. The PWR nuclear power plant instrumentation system probe test processing method of claim 1, further comprising:
and testing or calibrating the signal processing assembly according to the test data.
9. Experimental processing apparatus of pressurized water reactor nuclear power station instrumentation system detector, its characterized in that includes:
the data acquisition unit is used for acquiring index data of the detector;
the first data processing unit is used for amplifying and conditioning the index data;
the second data processing unit is used for carrying out operation processing on the amplified and conditioned index data to obtain test data;
a performance evaluation unit for evaluating the performance of the detector according to the test data; acquiring the counting rate of a pulse signal of a source range detector; calculating plateau characteristic data and discrimination threshold data of the source range detector according to the counting rate and the bias voltage of the source range detector; under the condition that the irradiation intensity of a radiation source is not changed and the discrimination threshold is not changed, a plateau characteristic curve corresponding to plateau characteristic data is obtained according to the change of the counting rate along with the bias voltage of the source range detector; keeping the neutron flux and the bias voltage unchanged, obtaining a relation curve between the counting rate of the source range detector and discrimination threshold data, discriminating a threshold curve, taking the discrimination threshold curve as a basis for evaluating the aging state of the source range detector, and tracking the aging trend of the detector;
based on a discrimination threshold curve of a source range detector, quantitatively identifying degradation of a detector flat area, and setting quantitative identification parameters; judging whether an inflection point exists in the curve according to a discrimination threshold curve, if the inflection point exists and is positioned before a discrimination value 3, judging whether the inflection point is positioned before a discrimination value 2, if the inflection point is positioned before the discrimination value 2, and the discrimination value 2 to 4 and the quantitative identification parameter are less than 60%, adjusting the discrimination value to be 3, and indicating that a source range channel and a probe are normal; if the inflection point is in front of the discrimination value 2, the discrimination value is from 2 to 4, and the quantitative identification parameter is not less than 60%, judging that the probe is aged by combining the high-pressure plateau characteristic curve, needing to replace the probe, and obtaining the discrimination threshold curve again; if the inflection point is before 3 and not before 2, the discrimination value is 3-5, and the quantitative identification parameter is not less than 60%, judging that the probe is aged by combining the high-voltage plateau characteristic curve, needing to replace the probe, and obtaining the discrimination threshold curve again; if the inflection point is not before 2 before 3, the discrimination value is 3-5, and the quantitative identification parameter is less than 60%, adjusting the discrimination value to be 4, and periodically checking the source range measurement channel under the condition that the drift of the source range measurement channel is acceptable; if the curve has no inflection point, the discrimination value is 2-4, and the quantitative identification parameter is not less than 60%, judging that the probe is aged by combining the high-pressure plateau characteristic curve, the probe needs to be replaced, and obtaining the discrimination threshold curve again; if the curve has no inflection point, the discrimination value is 2-4, and the quantitative identification parameter is less than 60%, adjusting the discrimination value to 3, and periodically checking the measurement channel under the condition that the drift of the measurement channel is acceptable; wherein the discrimination value is a scale value representing a discrimination threshold potentiometer.
10. The instrumentation probe test processing apparatus of a pressurized water reactor nuclear power plant according to claim 9, wherein said data acquisition unit comprises:
the pulse signal acquisition module is used for acquiring a pulse signal output by the source range detector;
and the current signal acquisition module is used for acquiring current signals of the intermediate range detector or the power range detector.
11. The instrumentation probe test processing apparatus of a pressurized water reactor nuclear power plant according to claim 9, wherein said first data processing unit comprises:
the pulse adjusting circuit is used for amplifying, shaping and discriminating the pulse signals;
and the current amplifying circuit is used for carrying out current-voltage I-V conversion and voltage amplification processing on the current signal.
12. The instrumentation probe test processing apparatus of a pressurized water reactor nuclear power plant according to claim 9, wherein said second data processing unit comprises:
the field programmable gate array FPGA circuit is used for acquiring the counting rate of a pulse signal of the source range detector and acquiring a plateau characteristic curve and a discrimination threshold curve of the source range detector according to the counting rate and the bias voltage of the source range detector; and the device is also used for calculating a current signal of the intermediate range detector and acquiring a plateau characteristic curve and a negative high-voltage curve of the intermediate range detector according to the current signal and the high-voltage signal of the intermediate range detector.
13. A probe test processing system comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor when executing the computer program implements the steps of the method of any one of claims 1 to 8.
14. A computer-readable storage medium, in which a computer program is stored which, when being executed by a processor, carries out the steps of the method according to any one of claims 1 to 8.
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| CN109406912A (en) * | 2018-12-13 | 2019-03-01 | 武汉瑞莱保能源技术有限公司 | A kind of detection system based on intermediate range signal |
| CN111929720B (en) * | 2020-07-13 | 2023-04-25 | 中广核核电运营有限公司 | Neutron detector performance detection method, device, system and computer equipment |
| CN112213766B (en) * | 2020-09-29 | 2023-10-20 | 中广核核电运营有限公司 | Neutron detector reliability verification method and device |
| CN113436766B (en) * | 2021-06-07 | 2023-05-26 | 中国核动力研究设计院 | Off-stack nuclear instrument system equipment for nuclear power plant |
| CN114530268B (en) * | 2022-01-25 | 2024-05-31 | 中国原子能科学研究院 | Method, system and computer readable storage medium for protecting reactor |
| CN115762831B (en) * | 2023-01-06 | 2023-04-04 | 中国工程物理研究院材料研究所 | Wide-range critical accident alarm device based on fission ionization chamber |
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