CN110850463A - Nuclear power station radioactivity monitoring method and device, control terminal and monitoring system - Google Patents

Nuclear power station radioactivity monitoring method and device, control terminal and monitoring system Download PDF

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CN110850463A
CN110850463A CN201910954282.1A CN201910954282A CN110850463A CN 110850463 A CN110850463 A CN 110850463A CN 201910954282 A CN201910954282 A CN 201910954282A CN 110850463 A CN110850463 A CN 110850463A
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radioactivity
background data
monitoring
nuclear power
data
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姚一正
林国强
朱存宝
阳立
游鑫俊
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Qunxing Import And Export Co Ltd
China General Nuclear Power Corp
CGN Power Co Ltd
Lingao Nuclear Power Co Ltd
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Qunxing Import And Export Co Ltd
China General Nuclear Power Corp
CGN Power Co Ltd
Lingao Nuclear Power Co Ltd
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    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/16—Measuring radiation intensity
    • G01T1/167—Measuring radioactive content of objects, e.g. contamination
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/003—Scintillation (flow) cells
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/16—Measuring radiation intensity
    • G01T1/20—Measuring radiation intensity with scintillation detectors
    • G01T1/203—Measuring radiation intensity with scintillation detectors the detector being made of plastics
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/16—Measuring radiation intensity
    • G01T1/20—Measuring radiation intensity with scintillation detectors
    • G01T1/208—Circuits specially adapted for scintillation detectors, e.g. for the photo-multiplier section
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T7/00—Details of radiation-measuring instruments
    • G01T7/12—Provision for actuation of an alarm
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/002—Detection of leaks
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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Abstract

The method, the device, the control terminal and the monitoring system for monitoring the radioactivity of the nuclear power station are suitable for the technical field of radiation protection of the nuclear power station, the radioactivity data of a monitoring area are obtained, and when the obtained radioactivity data are larger than or equal to an alarm threshold value, it is indicated that the intensity of radioactive substances is strong, and then radioactivity abnormity is determined. Therefore, the radioactivity monitoring method for the nuclear power station can accurately monitor radioactivity and is high in monitoring precision. And the alarm threshold is equal to the sum of the current background data and the current background data multiplied by a set percentage, or equal to the sum of the current background data and the square root of the current background data multiplied by a set scale factor, the alarm threshold is not set randomly but is associated with the current background data, the alarm threshold is associated with the background data, the monitoring precision can be further improved, and the current requirements for higher and higher monitoring precision are met.

Description

Nuclear power station radioactivity monitoring method and device, control terminal and monitoring system
Technical Field
The application belongs to the technical field of radiation protection of nuclear power plants, and particularly relates to a method and a device for monitoring radioactivity of a nuclear power plant, a control terminal and a monitoring system.
Background
Currently, the existing radioactivity monitoring methods are: and acquiring radioactivity data of the monitored area, and determining whether the radioactivity is abnormal or not according to the relation between the radioactivity data and the empirical value. Such a radioactivity monitoring method, in which the presence or absence of radioactivity abnormality is determined by an empirical value, has low monitoring accuracy.
Disclosure of Invention
In view of this, the embodiment of the present application provides a nuclear power plant radioactivity monitoring method, a nuclear power plant radioactivity monitoring device, a control terminal, and a nuclear power plant radioactivity monitoring system, so as to solve the problem that the existing nuclear power plant radioactivity monitoring method is low in monitoring accuracy.
In a first aspect, an embodiment of the present application provides a method for monitoring radioactivity in a nuclear power plant, including:
acquiring radioactivity data of a monitoring area;
comparing the radioactivity data to an alarm threshold, the alarm threshold being equal to the sum of the current background data and the increment; the increment is equal to the current background data multiplied by a set percentage, or equal to the square root of the current background data multiplied by a set scale factor;
determining a radiological anomaly when the radiological data is greater than or equal to the alarm threshold.
A second aspect of an embodiment of the present application provides a nuclear power plant radioactivity monitoring device, including:
the data acquisition module is used for acquiring radioactive data of the monitoring area;
a comparison module for comparing the radioactivity data with an alarm threshold, wherein the alarm threshold is equal to the sum of the current background data and an increment; the increment is equal to the current background data multiplied by a set percentage, or equal to the square root of the current background data multiplied by a set scale factor;
an anomaly determination module to determine a radiological anomaly when the radiological data is greater than or equal to the alarm threshold.
In a third aspect of the embodiments of the present application, a control terminal is provided, and includes a memory, a processor, and a computer program stored in the memory and executable on the processor, where the processor, when executing the computer program, implements the steps of the method for monitoring radioactivity in a nuclear power plant provided in the first aspect of the embodiments of the present application.
A fourth aspect of the embodiments of the present application provides a computer-readable storage medium, where a computer program is stored, and when the computer program is executed by a processor, the steps of the method for monitoring radioactivity in a nuclear power plant according to the first aspect of the embodiments of the present application are implemented.
A fifth aspect of an embodiment of the present application provides a nuclear power plant radioactivity monitoring system, including:
the radioactivity detection module is used for detecting radioactivity data of the monitoring area;
a control module; and
an alarm module;
the radioactivity detection module is connected with the control module in output, the control module is connected with the alarm module in output, and the control module is used for realizing the steps of the method for monitoring the radioactivity of the nuclear power station provided by the first aspect of the embodiment of the application.
A sixth aspect of embodiments of the present application provides a computer program product, which when run on a control terminal, causes the control terminal to execute the method for monitoring radioactivity in a nuclear power plant provided in the first aspect of embodiments of the present application.
Compared with the prior art, the implementation mode of the invention has the following beneficial effects: and when the acquired radioactivity data is greater than or equal to the alarm threshold value, the intensity of the radioactive substance is strong, and the radioactive abnormality is determined. Therefore, the radioactivity monitoring method for the nuclear power station can accurately monitor radioactivity and is high in monitoring precision. And the alarm threshold is equal to the current background data plus the current background data multiplied by a set percentage, or equal to the current background data plus the square root of the current background data multiplied by a set scale factor, so that the alarm threshold is not randomly set and is not an empirical value, but is associated with the current background data, if the background data changes, the alarm threshold can change along with the background data, and therefore, the monitoring precision can be further improved by associating the alarm threshold with the background data, and the requirement of higher and higher monitoring precision at present is met.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings required to be used in the description of the embodiments or the prior art will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present application, and it is obvious for those skilled in the art that other drawings can be obtained according to the drawings without inventive labor.
Fig. 1 is a schematic flow chart of a nuclear power plant radioactivity monitoring method according to an embodiment of the present application;
fig. 2 is a schematic structural diagram of a radioactivity monitoring system of a nuclear power plant according to a second embodiment of the present application;
fig. 3 is a schematic structural diagram of a radioactivity monitoring system of a nuclear power plant according to a second embodiment of the present application;
fig. 4 is a schematic structural diagram of a nuclear power plant radioactivity monitoring device provided in the third embodiment of the present application;
fig. 5 is a schematic structural diagram of a control terminal according to a fourth embodiment of the present application.
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 present application. It will be apparent, however, to one skilled in the art that the present application 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 application 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 present application herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the application. As used in the specification of the present application 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 understood that the order of writing each step in this embodiment does not mean the order of execution, and the order of execution of each process should be determined by its function and inherent logic, and should not constitute any limitation on the implementation process of the embodiment of the present invention.
In order to explain the technical means described in the present application, the following description will be given by way of specific embodiments.
Referring to fig. 1, it is a flowchart of an implementation process of a nuclear power plant radioactivity monitoring method provided in an embodiment of the present application, and for convenience of description, only parts related to the embodiment of the present application are shown.
The radioactivity monitoring method for the nuclear power station comprises the following steps:
step S101: radioactivity data of the monitored area is acquired.
In order to implement the nuclear power station radioactivity monitoring method, a nuclear power station radioactivity monitoring system is provided and comprises a radioactivity detection module and a control module. Defining a monitoring area, and the radioactivity monitoring system of the nuclear power plant is used for monitoring the radioactivity condition of the monitoring area. The monitoring area is then the monitoring area of the activity detection module. The output of the radioactivity detection module is connected with the control module. The radioactivity detection module is used for detecting radioactivity data of the monitoring area, and the radioactivity data can be understood as the radioactivity intensity of the radioactive substance. Since the radioactivity detecting module for detecting the radioactivity data of the monitored area is a conventional device, the present embodiment will not be described in detail.
Step S102: comparing the radioactivity data to an alarm threshold, the alarm threshold being equal to the sum of the current background data and the increment; the increment is equal to the current background data multiplied by a set percentage or equal to the square root of the current background data multiplied by a set scale factor.
The radioactivity detection module outputs the detected radioactivity data of the monitoring area to the control module. The control module has functions of data processing, analysis and control, and after acquiring the radioactivity data of the monitoring area sent by the radioactivity detection module, the control module compares the radioactivity data with an alarm threshold, wherein the alarm threshold is equal to the sum of the current background data (namely background counting rate, the same below) and an increment, the increment is a defined parameter and is equal to the multiplication of the current background data by a set percentage, or is equal to the multiplication of the square root of the current background data by a set scale factor, namely the alarm threshold has two calculation modes, namely the first mode: the alarm threshold is equal to the current background data plus the current background data multiplied by the set percentage, and the formula is as follows:
T＝N+N*e
wherein, T is an alarm threshold, N is current background data, e is a set percentage (of course, e is greater than 0), and a specific value of e is set according to actual needs.
And the second method comprises the following steps: the alarm threshold is equal to the current background data plus the square root of the current background data multiplied by a set scale factor, and the formula is as follows:
Figure BDA0002226755840000051
wherein, T is an alarm threshold, N is current background data, m is a set scale factor (m is a numerical value greater than 0, such as 3), and a specific value of m is set according to actual needs.
The alarm threshold value is closely related to the current background data, the relation indicates that the alarm threshold value is not set randomly, the alarm threshold value is larger than the background data, and the monitoring precision can be improved through the relation.
Optionally, in order to further improve the monitoring accuracy and meet the actual monitoring requirement, the background data participating in the calculation of the alarm threshold is updated according to a set time period (the specific value of the time period is set according to the actual requirement). And judging whether the background data obtained by updating is normal or not during each updating. Optionally, in each update, determining whether the updated background data is normal includes: for a certain update, if the background data obtained by the update meets the following formula, judging that the background data obtained by the update is normal:
Nb-a*n＜Nb’＜Nb+a*n
wherein N isb' is the background data obtained by the current update (i.e. N in the above); n is a radical ofbIs the average value of all background data obtained by updating before the update, namely the average value of the background data obtained by updating before the update and the initial background dataA value; a is a set background abnormal coefficient, n is a set deviation value (such as a standard deviation), and a and n are both values greater than 0, and can be set according to actual needs. From the above, the background data obtained from each update cannot deviate too much from the average.
Therefore, when background data is updated every time, the corresponding alarm threshold value is correspondingly changed so as to meet the actual situation.
An upper limit value (such as 50) and a lower limit value (such as 9500) of the background data can be set, the relationship between the updated background data and the upper limit value and the lower limit value is compared when the background data is updated each time, and when the updated background data is larger than the upper limit value or smaller than the lower limit value, an indication signal of background failure is given.
The background abnormal coefficient a is a parameter (for example, 5) for judging the fluctuation of the background, if the background change is too large (namely, the formula for judging whether the background data obtained by updating each time is normal is not satisfied), the background abnormal coefficient a can also give out the background abnormal even if the background change does not exceed the upper and lower limit ranges, and the parameter is obtained through a plurality of tests and does not need to be modified if not necessary.
As another embodiment, the background data may be updated in other updating manners, for example, after any one monitoring is completed, the background data is updated once each monitoring is completed, or the background data is updated once each system is started. Of course, the background data may also be a fixed value without updating under the condition of conforming to the actual monitoring.
Step S103: determining a radiological anomaly when the radiological data is greater than or equal to the alarm threshold.
When the radioactivity data is greater than or equal to the alarm threshold, the control module determines that the radioactivity is abnormal. Optionally, the nuclear power station radioactivity monitoring system further comprises an alarm module, the output of the control module is connected with the alarm module, and when the radioactivity abnormality is determined, the control module controls the alarm module to output an alarm signal. In the above, the control module may be set locally, and then, the corresponding control mode is a local control mode (i.e., local operation), and of course, the control module may also be a computer of a remote control center, and various data are transmitted to the computer of the remote control center, so that the remote control is realized through the computer of the remote control center.
And when the acquired radioactivity data is greater than or equal to the alarm threshold value, the intensity of the radioactive substance is strong, and the radioactive abnormality is determined. Therefore, the radioactivity monitoring method can accurately monitor radioactivity and has high monitoring precision. In addition, the alarm threshold value is not set at will and is not an empirical value, but is associated with the current background data, and the alarm threshold value changes correspondingly along with the updating of the background data, so that the monitoring precision can be further improved by associating the alarm threshold value with the background data, and the current requirements on higher and higher monitoring precision are met.
Referring to fig. 2, a schematic structural diagram of a nuclear power plant radioactivity monitoring system according to a second embodiment of the present application is shown. The nuclear power plant radioactivity monitoring system comprises a radioactivity detection module 201, a control module 202 and an alarm module 203. Defining a monitoring area, and the radioactivity monitoring system of the nuclear power plant is used for monitoring the radioactivity condition of the monitoring area. The output of the radioactivity detection module 201 is connected with the control module 202, and the output of the control module 202 is connected with the alarm module 203. The radioactivity detection module 201 is configured to detect radioactivity data of the monitoring area, and output the detected radioactivity data of the monitoring area to the control module 202. The control module 202 has data processing, analyzing, and controlling functions. After acquiring the radioactivity data of the monitoring area sent by the radioactivity detection module 201, the control module 202 compares the radioactivity data with an alarm threshold, where the alarm threshold is equal to the sum of the current background data (i.e., background count rate, the same applies below) and an increment, the increment is a defined parameter and is equal to the sum of the current background data multiplied by a set percentage, or is equal to the sum of the square root of the current background data multiplied by a set scale factor, that is, the alarm threshold has two calculation modes, the first mode is: the alarm threshold is equal to the current background data plus the current background data multiplied by the set percentage, and the formula is as follows:
T＝N+N*e
wherein, T is an alarm threshold, N is current background data, e is a set percentage (of course, e is greater than 0), and a specific value of e is set according to actual needs.
And the second method comprises the following steps: the alarm threshold is equal to the current background data plus the square root of the current background data multiplied by a set scale factor, and the formula is as follows:
Figure BDA0002226755840000071
wherein, T is an alarm threshold, N is current background data, m is a set scale factor (m is a numerical value greater than 0, such as 3), and a specific value of m is set according to actual needs.
When the radioactivity data is greater than or equal to the alarm threshold, the control module 202 determines that the radioactivity is abnormal, and optionally outputs an alarm signal to the alarm module 203. In addition, after the alarm signal is output, the radioactivity data detected by the radioactivity detection module 201 is automatically saved.
Optionally, in order to further improve the monitoring accuracy, the background data participating in the calculation of the alarm threshold is updated according to a set time period (a specific value of the time period is set according to actual needs), and whether the updated background data is normal is determined during each update. Optionally, the determining whether the updated background data is normal includes: for a certain update, if the background data obtained by the update meets the following formula, judging that the background data obtained by the update is normal:
Nb-a*n＜Nb’＜Nb+a*n
wherein N isb' is the background data obtained by the current update (i.e. N in the above); n is a radical ofbThe average value of all background data obtained by updating before the updating, namely the average value of the background data obtained by updating before the updating and the initial background data; a is a set background abnormal coefficient, n is a set deviation value (such as a standard deviation), and a and n are both values greater than 0, and can be set according to actual needs. As can be seen from the above, the background data obtained for each updateIt must not deviate too much from the average.
Therefore, when background data is updated every time, the corresponding alarm threshold value is correspondingly changed so as to meet the actual situation.
An upper limit value (such as 50) and a lower limit value (such as 9500) of the background data can be set, the relationship between the updated background data and the upper limit value and the lower limit value is compared when the background data is updated each time, and when the updated background data is larger than the upper limit value or smaller than the lower limit value, an indication signal of background failure is given.
The background abnormal coefficient a is a parameter (for example, 5) for judging the fluctuation of the background, if the background change is too large (namely, the formula for judging whether the background data obtained by updating each time is normal is not satisfied), the background abnormal coefficient a can also give out the background abnormal even if the background change does not exceed the upper and lower limit ranges, and the parameter is obtained through a plurality of tests and does not need to be modified if not necessary.
Of course, the radioactivity monitoring system of the nuclear power station further comprises a power supply module for providing a low-voltage direct-current power supply for the system.
As another embodiment, the background data may be updated in other updating manners, for example, after any one monitoring is completed, the background data is updated once each monitoring is completed, or the background data is updated once each system is started. Of course, the background data may also be a fixed value without updating under the condition of conforming to the actual monitoring.
Therefore, the radioactivity monitoring system of the nuclear power station can accurately monitor radioactivity and has high monitoring precision. Moreover, the related alarm threshold is not set randomly but is associated with the current background data, and the alarm threshold changes correspondingly with the updating of the background data, so that the monitoring precision can be further improved by associating the alarm threshold with the background data, and the current requirements on higher and higher monitoring precision are met.
Fig. 3 is a schematic structural diagram of a nuclear power plant radioactivity monitoring system according to a second embodiment of the present application. The nuclear power station radioactivity monitoring system is a vehicle channel type radioactivity monitoring system. The nuclear power plant radioactivity monitoring system comprises a radioactivity detection module, a control module 303, an alarm module 304 and a storage module 306. Defining a monitoring area, and the radioactivity monitoring system of the nuclear power plant is used for monitoring the radioactivity condition of the monitoring area.
The radioactivity detection module comprises a scintillator 301 and a photomultiplier 302, wherein the scintillator 301 is a large-area plastic scintillator and is used as a gamma ray detection medium. Generally, more than one activity detection module, for example, 4 activity detection modules, are provided, and when a plurality of activity detection modules are provided, the monitoring area surrounded by the plurality of scintillators 301 is the monitoring area defined above, and the monitoring area is specifically a passage surrounded by the plurality of scintillators 301 and through which a vehicle passes. The scintillator 301 detects gamma radioactive data of a monitoring area in real time, and the model of the scintillator 301 is as follows: EJ200/BC 804; each scintillator 301 is provided with two photomultiplier tubes 302, the efficiency of which is 30% higher than that of a single photomultiplier tube, and the photomultiplier tubes 302 adopt high-performance photomultiplier tubes (PMT) produced by HAMAMATSU (HAMAMATSU) as photoelectric conversion devices. The scintillator 301 is connected to a photomultiplier tube 302. The radioactivity monitoring system fully utilizes the advantage of short decay time (about 2.1ns) of the plastic scintillator to improve the performance of high-intensity radiation measurement. The operating principle of the scintillator 301 and the photomultiplier tube 302 is as follows: the incident radiation is lost and energy is deposited in the scintillator 301, so that ionization excitation of atoms (or ions, molecules) in the scintillator 301 is caused, then excited particles are excited to emit scintillation photons with the wavelength close to visible light, the scintillation photons are emitted into a photocathode of the photomultiplier tube 302 through a light guide and emit photoelectrons, the photoelectrons are accelerated to move under the action of a strong electric field between the emitter stages and bombard the next emitter stage, more photoelectrons are emitted, and then multiplication of the photoelectrons is realized until the photoelectrons finally reach the anode and generate a signal in an output circuit.
The control module 303 includes an amplification forming unit, a single-channel unit, a scaler, and a data processing unit, which are connected in sequence. The enlargement forming unit includes: the two signal following boards process the front signals to ensure that the signals can meet the transmission at a certain distance; two-way signal discriminator. The single-channel unit and the scaler form a single-channel scaling processing system for processing the amplified and shaped signal. The data processing unit adopts an ARM9 processor to support multi-path signal input. Since the amplification shaping unit, the single-channel unit, the scaler, and the data processing unit are all existing devices, they will not be described herein. In this embodiment, the control module 303 is installed locally, i.e. on the corresponding local device, so as to avoid that the control module 303 is not located locally, which may cause the related device to be unavailable due to signal transmission failure between the control module 303 and the radioactivity detection module. In addition, the control module 303 transmits various data to a computer of the remote control center through communication methods such as optical fibers or internet of things.
Optionally, the alarm module 304 includes an audio alarm device and an optical alarm device, where the audio alarm device includes a buzzer and an alarm speaker, and the buzzer and the alarm speaker do not operate under the condition of no alarm, and operate when the radiation exceeds the standard; the light alarm equipment comprises outdoor rotary flashing indicator lamps (one traffic light respectively) and status indicator lamps, the status indicator lamps comprise an operation indicator lamp (green), a fault indicator lamp (yellow) and an alarm indicator lamp (red), under the condition of no alarm, the green flashing of the outdoor rotary flashing indicator lamps indicates that a vehicle can normally pass through, and if radiation exceeds the standard, the red indicator lamps of the outdoor rotary flashing indicator lamps flash.
The photomultiplier 302 is connected with an amplifying and shaping unit in the control module 303 through an RS485 bus output, and a data processing unit in the control module 303 is connected with an alarm module 304 through an output.
The storage module 306 is used for storing the radioactivity data (i.e. the radioactivity data of the vehicle) detected by the scintillator 301 and the photomultiplier tube 302, the comparison result of the radioactivity data and the alarm threshold value, and the like. The data storage time of the storage module 306 is set according to actual needs, and the storage module 306 may be a conventional memory.
The nuclear power station radioactivity monitoring system further comprises a vehicle monitoring module 305, and the output of the vehicle monitoring module 305 is connected with a data processing unit in the control module 303. The vehicle monitoring module 305 is configured to monitor whether a vehicle enters a monitoring area, and optionally, the vehicle monitoring module 305 includes at least one of an infrared correlation sensor, a ground coil sensor, and a license plate recognition camera. Wherein, infrared correlation sensor comprises two pairs of infrared correlation photoelectric sensor (every contains to throw light end and photic end to infrared correlation photoelectric sensor), and when the vehicle entered into monitoring area, the infrared ray that the sensor sent was sheltered from, and infrared correlation sensor outputs occupation signal, shows that monitoring area has the vehicle. And the infrared correlation sensor can also have a speed measurement function, the two pairs of sensors acquire the passing time of the vehicle, and the passing speed of the vehicle can be obtained by dividing the horizontal distance between the two pairs of sensors by the time interval of the sequential triggering of the vehicle. The model of the infrared correlation sensor is E3F1-TP 12. The laying mode of ground induction coil sensor and the working process of carrying out vehicle detection according to ground induction coil sensor belong to prior art, and this embodiment is no longer repeated, and in this embodiment, two ground induction coil sensors can be arranged at the front and back interval, can detect the speed of vehicle. The license plate recognition camera has a license plate number recognition function, monitors the image of the monitored area in real time, recognizes the license plate when the vehicle approaches the monitored area, and outputs the license plate information to the data processing unit in the control module 303. The infrared correlation sensor, the ground induction coil sensor and the license plate recognition camera can be partially or completely installed according to actual needs. In the above, the measured vehicle speed can be displayed on site, and when the vehicle speed exceeds the speed limit, the vehicle can give an alarm, so that the vehicle can be monitored on site conveniently. Moreover, the vehicle speed may also be stored in the memory module 306 and/or on a computer at a remote control center.
The vehicle monitoring module 305 monitors whether the vehicle enters a monitored area. When the vehicle monitoring module 305 monitors that the vehicle enters the monitoring area, the control module 303 wakes up the system to be switched to a measurement state, the radioactivity monitoring system starts to monitor the radiation condition of the vehicle, the scintillator 301 and the photomultiplier tube 302 detect the radioactivity data of the monitoring area, and send the detected radioactivity data to the control module 303, and the control module 303 processes the radioactivity data after acquiring the radioactivity data, specifically: firstly, performing data processing on radioactivity data, and then comparing the processed radioactivity data with an alarm threshold, wherein the alarm threshold is equal to the sum of current background data (namely background counting rate, the same applies below) and an increment, the increment is a defined parameter and is equal to the multiplication of the current background data by a set percentage, or is equal to the multiplication of the square root of the current background data by a set scale factor, namely the alarm threshold has two calculation modes, namely the first mode: the alarm threshold is equal to the current background data plus the current background data multiplied by the set percentage, and the formula is as follows:
T＝N+N*e
wherein, T is an alarm threshold, N is current background data, e is a set percentage (of course, e is greater than 0), and a specific value of e is set according to actual needs.
And the second method comprises the following steps: the alarm threshold is equal to the current background data plus the square root of the current background data multiplied by a set scale factor, and the formula is as follows:
wherein, T is an alarm threshold, N is current background data, m is a set scale factor (m is a numerical value greater than 0, such as 3), and a specific value of m is set according to actual needs. Such as: when the current background data N is 1000,
Figure BDA0002226755840000122
as an embodiment, for cobalt 60 radiation, the calculated alarm threshold may be 50000 Bq.
When the radioactivity data is greater than or equal to the alarm threshold, which indicates that the radioactivity level of the vehicle exceeds the standard, the control module 303 outputs an alarm signal to the alarm module 304.
Therefore, when background data is updated every time, the corresponding alarm threshold value is correspondingly changed so as to meet the actual situation.
The background data participating in the alarm threshold calculation is updated according to a set time period (the specific value of the time period is set according to actual needs). Moreover, at each time of updating, whether the updated background data is normal is judged, and a specific means for judging whether the updated background data is normal is given as follows:
for a certain update, if the background data obtained by the update meets the following formula, judging that the background data obtained by the update is normal:
Nb-a*n＜Nb’＜Nb+a*n
wherein N isb' is the background data obtained by the current update (i.e. N in the above); n is a radical ofbThe average value of all background data obtained by updating before the updating, namely the average value of the background data obtained by updating before the updating and the initial background data; a is a set background abnormal coefficient, n is a set deviation value (such as a standard deviation), and a and n are both values greater than 0, and can be set according to actual needs. From the above, the background data obtained from each update cannot deviate too much from the average.
An upper limit value (such as 50) and a lower limit value (such as 9500) of the background data can be set, the relationship between the updated background data and the upper limit value and the lower limit value is compared when the background data is updated each time, and when the updated background data is larger than the upper limit value or smaller than the lower limit value, an indication signal of background failure is given.
The background abnormal coefficient a is a parameter (for example, 5) for judging the fluctuation of the background, if the background change is too large (namely, the formula for judging whether the background data obtained by updating each time is normal is not satisfied), the background abnormal coefficient a can also give out the background abnormal even if the background change does not exceed the upper and lower limit ranges, and the parameter is obtained through a plurality of tests and does not need to be modified if not necessary.
As another embodiment, the background data may be updated in other updating manners, for example, after any one monitoring is completed, the background data is updated once each monitoring is completed, or the background data is updated once each system is started. Of course, the background data may also be a fixed value without updating under the condition of conforming to the actual monitoring.
Of course, the radioactivity monitoring system of the nuclear power station further comprises a power supply module for providing a low-voltage direct-current power supply for the system.
The radioactivity monitoring system of the nuclear power station can also adopt reliable shielding measures to effectively prevent the interference of an external electromagnetic field; meanwhile, the influence of internal noise is eliminated by adopting an effective noise processing technology.
In addition, the height of the measuring object of the radioactivity monitoring system of the nuclear power station is generally 60cm-400cm, including cars and containers, and the detection precision of the radioactivity monitoring system of the nuclear power station can meet the requirement within the height range of the measuring object.
Therefore, the radioactivity monitoring system of the nuclear power station can accurately monitor radioactivity and has high monitoring precision. Moreover, the related alarm threshold is not set randomly but is associated with the current background data, and the alarm threshold changes correspondingly with the updating of the background data, so that the monitoring precision can be further improved by associating the alarm threshold with the background data, and the current requirements on higher and higher monitoring precision are met.
Corresponding to the nuclear power plant radioactivity monitoring method described in the foregoing embodiment of the nuclear power plant radioactivity monitoring method, fig. 4 shows a block diagram of a nuclear power plant radioactivity monitoring apparatus provided in the third embodiment of the present application, and for convenience of description, only the parts related to the embodiment of the present application are shown.
Referring to fig. 4, a nuclear power plant radioactivity monitoring device 400 includes:
a data acquisition module 401, configured to acquire radioactivity data of a monitoring area;
a comparison module 402 configured to compare the radioactivity data with an alarm threshold, where the alarm threshold is equal to a sum of current background data and an increment; the increment is equal to the current background data multiplied by a set percentage, or equal to the square root of the current background data multiplied by a set scale factor;
an anomaly determination module 403 for determining a radioactive anomaly when the radioactivity data is greater than or equal to the alarm threshold.
Optionally, an alarm signal is output when a radiological anomaly is determined.
Optionally, in order to further improve the monitoring accuracy and meet the actual monitoring requirement, the background data participating in the calculation of the alarm threshold is updated according to a set time period (the specific value of the time period is set according to the actual requirement), and whether the updated background data is normal is judged during each update. Optionally, in each update, determining whether the updated background data is normal includes: for a certain update, if the background data obtained by the update meets the following formula, judging that the background data obtained by the update is normal:
Nb-a*n＜Nb’＜Nb+a*n
wherein N isb' is the background data obtained by the current update (i.e. N in the above); n is a radical ofbThe average value of all background data obtained by updating before the updating, namely the average value of the background data obtained by updating before the updating and the initial background data; a is a set background abnormal coefficient, n is a set deviation value (such as a standard deviation), and a and n are both values greater than 0, and can be set according to actual needs. From the above, the background data obtained from each update cannot deviate too much from the average.
Therefore, when background data is updated every time, the corresponding alarm threshold value is correspondingly changed so as to meet the actual situation.
It should be noted that, because the contents of information interaction, execution process, and the like between the above-mentioned devices/modules are based on the same concept as that of the embodiment of the method for monitoring radioactivity of a nuclear power plant of the present application, specific functions and technical effects thereof may be referred to specifically in the section of the embodiment of the method for monitoring radioactivity of a nuclear power plant, and details thereof are not described herein again.
It is clearly understood by those skilled in the art that, for convenience and simplicity of description, the above division of the functional modules is merely used as an example, and in practical applications, the above function distribution may be performed by different functional modules according to needs, that is, the internal structure of the nuclear power plant radioactivity monitoring apparatus 400 is divided into different functional 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. For the specific working process of each functional module, reference may be made to the corresponding process in the foregoing embodiment of the method for monitoring radioactivity in a nuclear power plant, and details are not described here again.
Fig. 5 is a schematic structural diagram of a control terminal according to a fourth embodiment of the present application, and as shown in fig. 5, the control terminal 500 includes: a processor 502, a memory 501, and a computer program 503 stored in the memory 501 and executable on the processor 502. The processor 502, when executing the computer program 503, implements the implementation steps of the nuclear power plant radioactivity monitoring method described above, i.e., the steps shown in fig. 1.
The specific implementation process of the control terminal 500 can be referred to the embodiment of the nuclear power plant radioactivity monitoring method above.
Illustratively, the computer program 503 may be partitioned into one or more modules/units that are stored in the memory 501 and executed by the processor 502 to accomplish the present application. The one or more modules/units may be a series of computer program instruction segments capable of performing specific functions, which are used to describe the execution process of the computer program 503 in the control terminal 500.
The control terminal 500 may be a desktop computer, a notebook, a palm computer, or other computing devices. The control terminal 500 may include, but is not limited to, a processor and a memory. Those skilled in the art will appreciate that fig. 5 is only an example of a control terminal 500 and does not constitute a limitation of the control terminal 500, and may include more or less components than those shown, or combine some of the components, or different components, for example, the control terminal 500 may further include input-output devices, network access devices, buses, etc.
The Processor 502 may be a CPU (Central Processing Unit), other general-purpose Processor, a DSP (Digital Signal Processor), an ASIC (application specific Integrated Circuit), an FPGA (Field-Programmable Gate Array), 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 501 may be an internal storage unit of the control terminal 500, such as a hard disk or a memory. The memory 501 may also be an external storage device of the control terminal 500, such as a plug-in hard disk, SMC (smart storage Card), SD (Secure Digital Card), Flash Card, or the like provided on the control terminal 500. Further, the memory 501 may also include both an internal storage unit of the control terminal 500 and an external storage device. The memory 501 is used for storing computer programs 503 as well as other programs and data needed for controlling the terminal 500. The memory 501 may also be used to temporarily store data that has been output or is to be output.
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 in the above control method embodiments may also be implemented by a computer program to instruct related hardware, where the computer program may be stored in a computer readable storage medium, and when the computer program is executed by a processor, the computer program may implement the steps of the implementation processes in the above control method embodiments. 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, ROM (Read-Only Memory), RAM (Random Access Memory), electrical carrier wave signal, telecommunication signal, software distribution medium, etc. It should be noted that the computer readable medium may contain content that is subject to appropriate increase or decrease as required by legislation and patent practice in jurisdictions, for example, in some jurisdictions, computer readable media does not include electrical carrier signals and telecommunications signals as is required by legislation and patent practice.
The above embodiments are only used for illustrating the technical solutions of the present application, and not for limiting the same; although the present application 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 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 application and are intended to be included within the scope of the present application.

Claims (10)

1. A nuclear power plant radioactivity monitoring method is characterized by comprising the following steps:
acquiring radioactivity data of a monitoring area;
comparing the radioactivity data to an alarm threshold, the alarm threshold being equal to the sum of the current background data and the increment; the increment is equal to the current background data multiplied by a set percentage, or equal to the square root of the current background data multiplied by a set scale factor;
determining a radiological anomaly when the radiological data is greater than or equal to the alarm threshold.
2. The nuclear power plant radioactivity monitoring method according to claim 1, wherein when the radioactivity anomaly is determined, an alarm signal is output.
3. The method for monitoring radioactivity in nuclear power plant according to claim 1 or 2, wherein the background data is updated according to a set time period, and at each update, whether the updated background data is normal is judged.
4. The nuclear power plant radioactivity monitoring method of claim 3, wherein the step of determining whether the updated background data is normal at each update comprises: for a certain update, if the background data obtained by the update meets the following formula, judging that the background data obtained by the update is normal:
Nb-a*n＜Nb’＜Nb+a*n
wherein N isb' for the background data obtained for this update, NbAnd a is the average value of all background data obtained by updating before the updating, a is a set background abnormal coefficient, and n is a set deviation value.
5. A nuclear power plant radioactivity monitoring device, comprising:
the data acquisition module is used for acquiring radioactive data of the monitoring area;
a comparison module for comparing the radioactivity data with an alarm threshold, wherein the alarm threshold is equal to the sum of the current background data and an increment; the increment is equal to the current background data multiplied by a set percentage, or equal to the square root of the current background data multiplied by a set scale factor;
an anomaly determination module to determine a radiological anomaly when the radiological data is greater than or equal to the alarm threshold.
6. A control terminal comprising a memory, a processor and a computer program stored in said memory and executable on said processor, characterized in that said processor, when executing said computer program, carries out the steps of the nuclear power plant radioactivity monitoring method according to any of claims 1-4.
7. 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 for monitoring radioactivity in a nuclear power plant as claimed in any one of claims 1 to 4.
8. A nuclear power plant radioactivity monitoring system, comprising:
the radioactivity detection module is used for detecting radioactivity data of the monitoring area;
a control module; and
an alarm module;
the radioactivity detection module is connected with the control module in output, the control module is connected with the alarm module in output, and the control module is used for realizing the steps of the radioactivity monitoring method of the nuclear power station as claimed in any one of claims 1 to 4.
9. The nuclear power plant radioactivity monitoring system of claim 8, wherein the radioactivity detection module comprises a scintillator and a photomultiplier tube, the scintillator being coupled to the photomultiplier tube, the photomultiplier tube output being coupled to the control module.
10. The nuclear power plant radioactivity monitoring system of claim 8 or 9, further comprising a storage module for storing the radioactivity data, the control module output being connected to the storage module.
CN201910954282.1A 2019-10-09 2019-10-09 Nuclear power station radioactivity monitoring method and device, control terminal and monitoring system Pending CN110850463A (en)

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Application publication date: 20200228