CN110749914B - Nuclear power station gamma-ray radioactive pollution monitoring system - Google Patents
Nuclear power station gamma-ray radioactive pollution monitoring system Download PDFInfo
- Publication number
- CN110749914B CN110749914B CN201910954293.XA CN201910954293A CN110749914B CN 110749914 B CN110749914 B CN 110749914B CN 201910954293 A CN201910954293 A CN 201910954293A CN 110749914 B CN110749914 B CN 110749914B
- Authority
- CN
- China
- Prior art keywords
- ray
- gamma
- frame
- detection signal
- monitoring
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Classifications
-
- 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
- G01T1/16—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
- G01T1/24—Measuring radiation intensity with semiconductor detectors
- G01T1/248—Silicon photomultipliers [SiPM], e.g. an avalanche photodiode [APD] array on a common Si substrate
Abstract
The application belongs to the technical field of nuclear power station radiation protection, and provides a nuclear power station gamma-ray radioactive pollution monitoring system, which comprises: a radiation monitoring access door comprising: the gamma-ray detector comprises a first frame and a second frame which are oppositely arranged along the vertical direction, wherein a set number of gamma-ray detectors are respectively arranged on the opposite surfaces of the first frame and the second frame in parallel along the vertical direction; the bottom (third frame) and the top (fourth frame) are respectively provided with a gamma-ray detector; the main control unit is used for respectively acquiring a first detection signal of a first row of gamma-ray detectors and a second detection signal of a second row of gamma-ray detectors in the gamma-ray detectors, and acquiring personnel passing information of the ray monitoring passage door based on the first detection signal and the second detection signal, so that the high-sensitivity ray monitoring requirement under the condition of large flow of people is improved, the full-coverage non-blind spot of measurement is ensured, and the passing speed is improved.
Description
Technical Field
The application belongs to the technical field of radiation protection of nuclear power plants, and particularly relates to a gamma-ray radioactive pollution monitoring system for a nuclear power plant.
Background
Due to the radioactive nature of the nuclear material, nuclear reactions and the use of nuclear materials generally require the installation of specific locations to be performed. Personnel working in a nuclear power plant or other nuclear facility plant area will inevitably physically have the potential to carry radioactive elements.
Therefore, it is usually necessary to detect radioactive rays of people entering and exiting the factory or factory building to check radioactive materials possibly carried by the people entering and exiting the factory or factory building, so as to ensure safety.
The existing ray detection equipment only has a simple ray detection function generally, and cannot meet the ray detection requirement under the condition of large flow of people under the condition of a large number of equipped personnel in a factory.
Disclosure of Invention
In view of this, the embodiment of the present application provides a system for monitoring gamma-ray radioactive contamination of a nuclear power station, so as to solve the problem that the existing radiation detection equipment generally only has a simple radiation detection function, and cannot meet the radiation detection requirement under the condition of a large amount of personnel in a plant area.
The embodiment of the application provides a nuclear power station gamma-ray radioactive pollution monitoring system, which comprises:
a radiation monitoring access door comprising: the gamma-ray detector comprises a first frame and a second frame which are oppositely arranged along the vertical direction, wherein a set number of gamma-ray detectors are respectively arranged on the opposite surfaces of the first frame and the second frame in parallel along the vertical direction;
and the main control unit is connected with the gamma-ray detectors and is used for respectively acquiring a first detection signal of a first row of gamma-ray detectors and a second detection signal of a second row of gamma-ray detectors in the gamma-ray detectors, which are arranged in parallel, and acquiring personnel passing information of the ray monitoring access door based on the first detection signal and the second detection signal.
Optionally, the main control unit is specifically configured to:
respectively recording the acquisition time of the first detection signal and the acquisition time of the second detection signal, determining that the passing direction of the person is a first direction when the acquisition time of the first detection signal is earlier than that of the second detection signal, and determining that the passing direction of the person is a second direction opposite to the first direction when the acquisition time of the first detection signal is later than that of the second detection signal.
Optionally, the system for monitoring gamma-ray radioactive contamination of a nuclear power plant further comprises:
the first infrared sensors and the second infrared sensors are arranged on the first frame or the second frame along the horizontal direction;
the main control unit is further configured to: acquiring first sensing information of the first infrared sensor and second sensing information of the second infrared sensor, respectively recording acquisition times of the first sensing signal and the second sensing information, determining that the passing direction of a person is a first direction when the acquisition time of the first sensing signal is earlier than the acquisition time of the second sensing signal and the acquisition time of the first detection signal is earlier than the acquisition time of the second detection signal, and determining that the passing direction of the person is a second direction opposite to the first direction when the acquisition time of the first sensing signal is later than the acquisition time of the second sensing signal and the acquisition time of the first detection signal is later than the acquisition time of the second detection signal.
Optionally, the main control unit is further configured to:
determining the passing speed of the personnel based on the acquisition time of the first detection signal and the second detection signal, and sending prompt information for prompting the personnel to detect again when the passing speed is greater than a threshold value; alternatively, the first and second electrodes may be,
when the first detection signal is detected and the second detection signal is not detected within a set time length, determining that the personnel of the ray monitoring access door are in a turning-back non-passing state; alternatively, the first and second electrodes may be,
and when the first detection signal is acquired and the second detection signal is acquired within a set time length, counting the acquisition times, and obtaining the personnel passing times based on the acquisition times.
Optionally, the gamma-ray detectors respectively arranged in parallel in the vertical direction include a first area detector arranged near the top of the radiation monitoring passage door, a second area detection area arranged near the bottom of the radiation monitoring passage door, and a third area detector located between the first area detector and the second area detector;
the main control unit is further configured to:
based on the first detection signal and the second detection signal, detection signals of the first area detector, the second area detector and the third area detector are respectively extracted, ray monitoring values of human body areas respectively corresponding to different area detectors are obtained, based on the ray monitoring values, the human body area corresponding to the maximum ray monitoring value is determined, and prompt information is sent.
Optionally, the main control unit is further configured to:
acquiring a ray counting rate of unit time based on the first detection signal and the second detection signal; and averaging the ray counting rate of each unit time in the set time length to be used as the background ray counting rate.
Optionally, the radiation monitoring access door further includes:
the third frame is connected with the bottom end of the first frame and the bottom end of the second frame, and the fourth frame is connected with the top end of the first frame and the top end of the second frame;
and the third frame and the fourth frame are provided with a set number of gamma-ray detectors.
Optionally, the third frame is embedded in a groove in the ground, and a surface of the third frame facing the fourth frame is flush with the ground.
Optionally, the system for monitoring gamma-ray radioactive contamination of a nuclear power plant further comprises:
the alarm device is connected with the main control unit and is used for executing the sending, responding or releasing operation of alarm information;
the ray monitoring access door is arranged at an outlet and/or an inlet of a nuclear facility factory area, and the alarm device is arranged in a guard room.
Optionally, on the opposite surfaces of the first frame and the second frame, the gamma-ray detectors arranged in parallel are arranged in a position-staggered manner; or the gamma-ray detectors arranged in parallel on the opposite surfaces of the first frame and the second frame are flush with each other.
Compared with the prior art, the embodiment of the application has the advantages that:
the main control unit is connected with the gamma-ray detectors on the door frames, under the condition that personnel pass through the main control unit, a first detection signal of a first row of gamma-ray detectors and a second detection signal of a second row of gamma-ray detectors in the gamma-ray detectors arranged on the two door frames in parallel can be obtained, and the parallel vertical arrangement of the probes arranged on the door frames on the two sides of the passage door is utilized to realize the personnel passing information of the ray monitoring passage door based on the first detection signal and the second detection signal, so that under the condition that the factory area is large and the number of the personnel is large, the personnel passing information is passed through, the ray monitoring requirement under the condition of large flow of people is improved, the full coverage of gamma-ray measurement is ensured, no blind spot is avoided, and the passing speed is greatly improved.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present application, 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 application, 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 block diagram of a system for monitoring gamma-ray radioactive contamination of a nuclear power plant according to an embodiment of the present application;
FIG. 2 is a schematic diagram of an arrangement of gamma ray detectors in a radiation monitoring access door according to an embodiment of the present application;
fig. 3 is a schematic view of another arrangement of gamma ray detectors in a radiation monitoring access door according to an 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, fig. 1 is a block diagram of a gamma-ray radioactive contamination monitoring system of a nuclear power plant according to an embodiment of the present application, and for convenience of explanation, only a part related to the embodiment of the present application is shown.
The gamma-ray radioactive pollution monitoring system of the nuclear power station is commonly called as a nuclear power station door-type gamma-ray radioactive pollution monitor. The gamma-ray radioactive pollution monitoring system for the nuclear power station provided in the embodiment specifically includes:
a radiation monitoring access door comprising: the gamma-ray detector comprises a first frame and a second frame which are oppositely arranged along the vertical direction, wherein a set number of gamma-ray detectors are respectively arranged on the opposite surfaces of the first frame and the second frame in parallel along the vertical direction;
and the main control unit is connected with the gamma-ray detectors and is used for respectively acquiring a first detection signal of a first row of gamma-ray detectors and a second detection signal of a second row of gamma-ray detectors in the gamma-ray detectors, which are arranged in parallel, and acquiring personnel passing information of the ray monitoring access door based on the first detection signal and the second detection signal.
In particular, the main object emphatically detected by the personnel whole-body gamma-ray radioactive pollution monitoring system is the common radionuclide of the nuclear power station.
In the structure, the ray monitoring access door is mainly arranged at the entrance and exit of a factory and a factory building of a nuclear power station or other nuclear facilities, and is used for rapidly monitoring the gamma radioactive pollution of the whole body of workers entering and exiting each area.
At least two rows of gamma-ray detectors which are arranged in parallel are arranged on the surface, facing the second frame, of the first frame from top to bottom along the vertical direction, the number of the gamma-ray detectors in each row is at least three, and the gamma-ray detectors can be distributed on the vertical middle line of the surface, facing the second frame, of the first frame. Similarly, at least two rows of gamma-ray detectors which are arranged in parallel are arranged on the surface of the second frame facing the third frame from top to bottom along the vertical direction, the number of the gamma-ray detectors in each row is at least three, and the gamma-ray detectors can be distributed on the vertical central line of the surface of the second frame facing the first frame.
Specifically, each gamma-ray detector consists of a coupling high-sensitivity photomultiplier, a high-voltage circuit module, a preamplifier circuit module, a signal processing, receiving and sending module and the like; the photomultiplier adopts a shockproof structural design; the electronic part of the detector has a fault feedback function, so that the control center and the upper computer can clearly know the working state of the probe.
The core component (probe) of the gamma-ray detector is a large-area high-sensitivity plastic scintillator, and the gamma-ray detector has a remote data transmission function and can be connected with a monitoring center computer, an alarm panel and other systems to complete a remote monitoring function.
In addition, in this structure, the main control unit specifically is located the top of ray monitoring access door, contains: the system comprises a main control board, an industrial personal computer, a power supply, an air switch, a power amplifier, a switch and the like.
The main control unit is another core component except the gamma-ray detector, controls related equipment such as a camera, an occupancy sensor, an industrial liquid crystal, a display screen and a sound device which are connected with the main control unit, and signals obtained by all the detectors are obtained by the main control unit. The main control unit can be selected to adopt a modular design, and is convenient to disassemble and maintain.
The occupancy sensor is a sensor using a photoelectric device as a conversion element, and can be used for monitoring non-electric quantity directly causing brightness change, such as light intensity, illuminance, radiation temperature measurement, gas component analysis and the like. The position occupying sensor of the ohm dragon can be adopted, and the position occupying sensor has the characteristics of non-contact, quick response, reliable performance and the like.
The main control board in the main control unit is connected with the detector main control board through an aviation plug, the gamma-ray detectors on the first frame and the second frame are respectively of an assembly structure which is connected in series, and the detectors arranged on different frames are connected with the probe main control board through buses, so that the communication of the probes on two sides is not influenced mutually, and the safety and the reliability of the system are greatly improved.
Another important task of the main control unit is to control the auxiliary sensor, including alarm indicator, occupancy sensor, camera, etc., the alarm indicator optionally is divided into 3 colors, respectively: red, yellow and green, and processes signals from the auxiliary sensors in real time to coordinate the work of each part.
The personnel passing information of the ray monitoring passage door acquired by the main control unit can be information such as passing direction, passing quantity, passing speed and passing time.
The main control unit is connected with the gamma-ray detectors on the door frames, under the condition that personnel pass through the door frames, a first detection signal of a first row of gamma-ray detectors and a second detection signal of a second row of gamma-ray detectors in the gamma-ray detectors which are arranged on the two door frames in parallel can be obtained, the parallel vertical arrangement of the probes which are arranged on the door frames on the two sides of the access door in parallel is utilized in the process, the waveform analysis of ray counting is carried out through the two vertical parallel arranged gamma-ray detectors, the in-out direction of a detected object is obtained, the personnel passing information of the ray monitoring access door is obtained on the basis of the first detection signal and the second detection signal, and under the condition that a plant area is provided with more large personnel, the personnel passing information is used for improving the ray monitoring requirement under the condition of large flow of the personnel.
Specifically, with reference to fig. 1, 2, and 3, the γ -ray detectors arranged in parallel on the side frames (i.e., the first frame and the second frame) on both sides of the access door compare the acquisition times of the detection signals of the two rows of detectors by acquiring the detection signals of the first row of detectors 1, 3, and 5 and the detection signals of the second row of detectors 2, 4, and 6, or by acquiring the detection signals of the first row of detectors 12, 8, and 10 and the detection signals of the second row of detectors 13, 11, and 9, or calculate the number of people in various situations such as entering, exiting, just entering, and returning by compiling a logical relationship using a combination of the infrared measurement signals 1 and 2, and record the numbers respectively. Or the direction and speed of the passage of the people can be determined and the number of the people coming in and going out can be counted by acquiring the difference between the combined detection signals of the detectors numbered 1, 3, 5, 8, 10 and 12 and the combined detection signals of the detectors numbered 2, 4, 6, 9, 11 and 13.
The logic optimization of the entering and exiting of the personnel must ensure that the entering and exiting direction judgment is accurate and reliable and records, including time; and judging the other conditions as abnormal conditions, and recording the abnormal conditions including time.
The numbers are convenient for positioning of each detector and combination and statistics of measurement data of each detector.
Specifically, the entering and exiting logic optimization may be performed as follows: triggering the sensors in the first row and then triggering the sensors in the second row to carry out 'go' logic, and recording the logic, including time; triggering the sensor in the first column to do 'out' logic and record after triggering the sensor in the second column, wherein the 'out' logic comprises time; and only triggering the sensors in one row, performing 'abnormal access' logic processing, recording time and acquiring various passing information of personnel.
On the opposite face of first frame and second frame, along the vertical direction respectively gamma-ray detector that sets up side by side for gamma-ray detector is two-sided parallel arrangement in the side door frame department of monitoring access door, ensures gamma-ray measurement full coverage no blind spot, has improved the speed of passing simultaneously greatly.
Further, as an optional implementation manner, the main control unit is specifically configured to:
respectively recording the acquisition time of the first detection signal and the acquisition time of the second detection signal, determining that the passing direction of the person is a first direction when the acquisition time of the first detection signal is earlier than that of the second detection signal, and determining that the passing direction of the person is a second direction opposite to the first direction when the acquisition time of the first detection signal is later than that of the second detection signal.
In this embodiment, when a person passes through, each gamma-ray detector transmits a detection signal to the main control unit when detecting a gamma-ray, and the acquisition time of the first detection signal and the acquisition time of the second detection signal recorded by the main control unit are substantially equivalent to the time when the corresponding gamma-ray detector detects a gamma-ray.
The first direction is a direction from the outside of the factory to the inside of the factory, and the second direction is a direction from the inside of the factory to the outside of the factory. The passing direction of personnel is acquired by detecting the time of gamma rays by the gamma ray detectors which are respectively arranged in parallel along the vertical direction, so that the personnel entering and exiting the plant area can be monitored and managed conveniently.
Further, the main control unit is further configured to: and determining the passing speed of the personnel based on the acquisition time of the first detection signal and the second detection signal, and sending prompt information for prompting the personnel to detect again when the passing speed is greater than a threshold value.
The main control unit detects the passing speed of the passing personnel through the recorded acquisition time of the first detection signal and the second detection signal, judges whether the passing speed is too high, and sends prompt information to remind the passing personnel to detect again when the passing speed is too high, so that the accuracy of a detection result is ensured.
For example, when a person passes through an access door, detecting a speed exceeding 5km/h, a prompt "you have speeding" is made and recorded, including time.
Or, the main control unit is further configured to: and when the first detection signal is acquired and the second detection signal is acquired within a set time length, counting the acquisition times, and obtaining the personnel passing times based on the acquisition times.
Or, the main control unit is further configured to: and when the first detection signal is detected and the second detection signal is not detected within a set time length, determining that the personnel of the ray monitoring access door is in a turning-back non-passing state.
The set time period may be set according to actual conditions, and may be, for example, three seconds.
When the first detection signal of the gamma-ray detector in the first row and the second detection signal of the gamma-ray detector in the second row are both acquired within a set time interval, a person is considered to pass through the ray monitoring access door, and the person is considered to pass through the ray monitoring access door once every time the situation is counted, at the moment, the counting number is increased by one, so that the counting and acquisition of the passing number of the person are realized. And when the first detection signal is acquired and the second detection signal is acquired within a set time length, counting the acquisition times, wherein the counted acquisition times are the personnel passing times.
If only the first detection signal of the gamma-ray detector in the first row is detected, but the second detection signal is not detected within the set time length, the current passer-by is considered to pass through half of the passage in the ray monitoring passage door and not pass through the passage completely.
The process realizes that different combinations of detection signals of the gamma-ray detector are utilized, the number of people entering, going out, just entering and returning (only triggering one infrared ray) and other various conditions are calculated through compiling a logical relation and are respectively recorded, so that the passing information of people under various conditions is conveniently recorded, and the monitoring of the passing people is comprehensively realized. Further, the gamma-ray radioactive pollution monitoring system for the nuclear power station also comprises:
and the first infrared sensor and the second infrared sensor are arranged on the first frame or the second frame along the horizontal direction.
Correspondingly, the main control unit is further configured to: acquiring first sensing information of the first infrared sensor and second sensing information of the second infrared sensor, respectively recording acquisition times of the first sensing signal and the second sensing information, determining that the passing direction of a person is a first direction when the acquisition time of the first sensing signal is earlier than the acquisition time of the second sensing signal and the acquisition time of the first detection signal is earlier than the acquisition time of the second detection signal, and determining that the passing direction of the person is a second direction opposite to the first direction when the acquisition time of the first sensing signal is later than the acquisition time of the second sensing signal and the acquisition time of the first detection signal is later than the acquisition time of the second detection signal.
The judgment and the acquisition of the passing direction of personnel are carried out together through the acquisition time of the sensing signal of the infrared sensor arranged on the ray monitoring passage door and the acquisition time of the detection signal of the gamma ray detector, the verification is formed between the acquisition time of the sensing signal of the infrared sensor and the acquisition time of the detection signal of the gamma ray detector, and the accuracy of the detection result is improved.
The infrared sensor can be an infrared occupancy sensor, the infrared occupancy sensors are respectively arranged in front of and behind the access door, different combinations of detection signals of the gamma-ray detector and sensing signals of the infrared sensors are utilized, the number of people entering, going out, just entering and returning (only triggering one infrared ray) and other various conditions are calculated through compiling logical relations, and the number of people is respectively recorded.
As an optional implementation manner, the γ -ray detectors respectively arranged in parallel in the vertical direction include a first area detector arranged near the top of the ray monitoring passage door, a second area detection area arranged near the bottom of the ray monitoring passage door, and a third area detector located between the first area detector and the second area detector;
correspondingly, the main control unit is further configured to: based on the first detection signal and the second detection signal, detection signals of the first area detector, the second area detector and the third area detector are respectively extracted, ray monitoring values of human body areas respectively corresponding to different area detectors are obtained, based on the ray monitoring values, the human body area corresponding to the maximum ray monitoring value is determined, and prompt information is sent.
In particular, different gamma ray detectors may be divided for measuring different body parts of the passing person.
For example, body part division: corresponding scale points are found for the head, shoulder, trunk, legs and feet according to standard 175 height, for example: referring to fig. 1, 2 and 3, it is determined which part of the human body is radioactive-contaminated by the combination of the measurement signals of the detectors of different parts, such as the top 4 radiation detectors for the head and shoulder parts + the top detector (if any) (i.e. detectors 1, 2, 12, 13 and 14), the middle 4 radiation detectors for the trunk parts (i.e. detectors 3, 4, 11 and 10), and the bottom 4 radiation detectors for the leg and foot parts + the bottom detector (i.e. detectors 5, 6, 8, 9 and 7). The detector combination of the human body detection parts can also have more combination modes, and is not limited to the above.
Based on the ray monitoring value, the human body area corresponding to the maximum ray monitoring value can be determined to send prompt information, for example, the corresponding indicator light is controlled to be on or flash, or prompt sound is sent, so that the human body is monitored in a subarea mode in a targeted mode, and the hidden danger troubleshooting efficiency is improved.
Further, whether the ray pollution on the body surface of the person exceeds a pollution control limit value or not can be determined through the total count of the 14 detectors, and corresponding reminding is carried out when the ray pollution exceeds the pollution control limit value.
Further, as an optional implementation manner, the main control unit is further configured to: acquiring a ray counting rate of unit time based on the first detection signal and the second detection signal; and averaging the ray counting rate of each unit time in the set time length to be used as the background ray counting rate.
In the process, the counting rate in unit time is averaged to obtain the counting rate in unit time; the counting rate of each unit time in a period of time is averaged to be used as the background counting rate of the ray monitoring channel gate, so that the calculation of a smooth background value is realized, and the subsequent main control unit can conveniently realize reasonable ray detection result processing based on the obtained detection signal of the gamma ray detector.
Further, background updating can be started 5 minutes after the personnel perform ray measurement through the access door; the previously stored count rate per unit time is updated every unit time at the latest count rate per unit time.
If the background counting is interrupted because the personnel pass through the channel door during the background updating or the background measuring, the data of the unit time background sampling is reserved, and the background sampling measurement is continued on the previous basis after the personnel pass through.
In addition, in order to reduce the background noise of the system, the inward side faces of the channel door (such as the face of the first frame facing the second frame, the face of the second frame facing the first frame, the face of the third frame facing the fourth frame, and the face of the fourth frame facing the third frame) can be made of aluminum materials with low atomic number, and the other faces are shielded by low-background old lead with the thickness of 25mm, so as to ensure effective shielding of the background, reduce background counting, improve detection sensitivity and measurement reliability, and particularly in the area with high radiation background, the detection system can meet the higher requirement (Co-60, below 3000 Bq) for detecting the surface pollution of a human body, and improve the detection performance of the channel door.
And the lead material attachment part of the shell of the passage door is made of stainless steel, so that the passage door is corrosion-resistant and has prolonged service life.
Further, optionally, the radiation monitoring access door further includes:
the third frame is connected with the bottom end of the first frame and the bottom end of the second frame, and the fourth frame is connected with the top end of the first frame and the top end of the second frame; and the third frame and the fourth frame are provided with a set number of gamma-ray detectors.
Referring to fig. 1, 2 and 3, the gamma ray detector is a core component of the system, and the length, width and thickness of the detector may be 300mm, 400mm, 50mm or 400mm, 50mm, or the length and width may be increased according to the size of the door frame, so as to cover the whole door frame of the detector, thereby improving the detection efficiency.
Specifically, this set of system can set up 14 detectors altogether, wherein every side respectively contains 6 probes on the frame of passway door both sides, bottom frame and top frame respectively contain 1 probe, realize the full-length all-round no dead angle's of personnel radiographic inspection when personnel pass through the door frame, and carry out the mode that the detector was arranged wholly on passway door both sides frame, bottom frame and top frame, can make monitoring system have even unanimous gamma-ray detection efficiency on the well axial plane that is on a parallel with two door frames, every position can both reach the requirement of minimum detection lower limit, thereby realize the detection at full-length all-round no dead angle.
In a specific implementation process, optionally, the sizes of the probes of the gamma ray detectors arranged in the vertical direction on the first frame and the second frame on the two sides of the passage door are different, the top probe (numbered 1, 2, 12 and 13) is a plastic scintillator with the size of 400mm x 50mm, the middle probe and the lower probe (numbered 3, 4, 10, 11 and 5, 6, 8 and 9) are plastic scintillators with the size of 300mm x 400mm x 50mm, and the bottom probe and the top probe (numbered 7 and 14) are plastic scintillators with the size of 400mm x 50mm, so that actual detection requirements are met.
Optionally, a third frame is embedded in a groove in the ground, and a surface of the third frame facing the fourth frame is flush with the ground.
The door passageway is the main personnel passageway in factory, and for preventing that the personnel of taking place from getting into to tumble or spraining industrial injury time such as foot takes place, the door is arranged for the formula of sinking, and the upper surface of door lower frame flushes with ground.
Further, the gamma-ray radioactive pollution monitoring system for the nuclear power station also comprises:
the alarm device is connected with the main control unit and is used for executing the sending, responding or releasing operation of alarm information; the ray monitoring access door is arranged at an outlet and/or an inlet of a nuclear facility factory area, and the alarm device is arranged in a guard room.
The alarm device is used for giving an alarm, eliminating the alarm, and the like. For example, the alarm device gives an alarm by sound corresponding to the C3 passage door, the device displays red to prompt 'pollution found', the alarm device sends out alarm information, a confirmation key can be pressed on the alarm device subsequently to make the sound disappear, the color and the action in the indicator lamp are kept unchanged, and the indicator lamp on the alarm device of the guard room is recovered to be normal after the confirmation key is pressed at the passage door. The alarm event can be recorded at the same time, a display screen can be set, and an event recording list is added on a related interface, such as the side position of the interface, so that the visual viewing is convenient.
Further, optionally, as shown in fig. 2 and fig. 3, on the opposite surfaces of the first frame and the second frame, the γ -ray detectors arranged in parallel are arranged in a staggered manner; or the gamma-ray detectors arranged in parallel on the opposite surfaces of the first frame and the second frame are flush with each other.
The gamma-ray detectors are respectively arranged on the surface, facing the second frame, of the first frame in parallel along the vertical direction, the gamma-ray detectors in different columns can be arranged in a position staggered mode, intervals are formed among the gamma-ray detectors in the same column, and the positions of the gamma-ray detectors in adjacent columns are right opposite to gaps among the gamma-ray detectors in the column. The arrangement of the gamma ray detectors arranged on the surface of the second frame facing the first frame is the same, and the description is omitted. The detection performance is greatly improved by adopting a plurality of large-area gamma-ray detectors which are arranged in a complementary way.
Or the gamma-ray detectors which are respectively arranged in parallel along the vertical direction on the surface of the first frame facing the second frame do not have intervals between the gamma-ray detectors in the same column, and the gamma-ray detectors in different columns are arranged in parallel. The arrangement of the gamma ray detectors arranged on the surface of the second frame facing the first frame is the same, and the description is omitted. The detection accuracy is improved by the double-row gamma-ray detector.
Can be selected according to actual needs.
And monitoring cameras are respectively arranged at the doorways on the two sides of the ray monitoring access door.
The camera can be selected to be a network camera, the operation is stable, and the monitoring precision is high. The front and the back of the ray monitoring access door are respectively provided with a network camera, so that pedestrians can be monitored in two directions. When the pedestrian has pollution on one's body, supervisory equipment sends audible and visual warning, and the picture of setting for the number can be taken a candid photograph automatically and is preserved to the network camera simultaneously, convenient further analysis, and the two camera designs of system, no matter what the personnel pass in and out accomplish to report to the police and make a video recording do not have the blind spot.
Furthermore, the personnel pollution alarm signal of the ray monitoring passage door can be linked with the revolving door of the plant area, and the plant area revolving door is controlled to be closed when the alarm signal for indicating the existence of pollution appears, so that possible pollution personnel can be prevented from leaving the control area out of control.
In the embodiment of the present application, the integrated module/unit may be stored in a computer-readable storage medium if it is implemented in the form of a software functional unit and sold or used as a separate product. 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 to complete, where the computer program may be stored in a computer readable storage medium, and when the computer program is executed by the main control unit, 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 gamma-ray radioactive contamination monitoring system, comprising:
a radiation monitoring access door comprising: the gamma-ray detector comprises a first frame and a second frame which are oppositely arranged along the vertical direction, wherein a set number of gamma-ray detectors are respectively arranged on the opposite surfaces of the first frame and the second frame in parallel along the vertical direction;
the main control unit is connected with the gamma-ray detectors and is used for respectively acquiring a first detection signal of a first row of gamma-ray detectors and a second detection signal of a second row of gamma-ray detectors in the gamma-ray detectors which are arranged in parallel and acquiring personnel passing information of the ray monitoring passage door based on the first detection signal and the second detection signal; the main control unit is specifically positioned at the top of the ray monitoring access door;
the main control unit is further configured to:
determining the passing speed of the personnel based on the acquisition time of the first detection signal and the second detection signal, and sending prompt information for prompting the personnel to detect again when the passing speed is greater than a threshold value; alternatively, the first and second electrodes may be,
and when the first detection signal is detected and the second detection signal is not detected within a set time length, determining that the personnel of the ray monitoring access door is in a turning-back non-passing state.
2. The nuclear power plant gamma ray radioactive contamination monitoring system of claim 1, wherein the master control unit is specifically configured to:
respectively recording the acquisition time of the first detection signal and the acquisition time of the second detection signal, determining that the passing direction of the person is a first direction when the acquisition time of the first detection signal is earlier than that of the second detection signal, and determining that the passing direction of the person is a second direction opposite to the first direction when the acquisition time of the first detection signal is later than that of the second detection signal.
3. The nuclear power plant gamma ray radioactive contamination monitoring system of claim 2, further comprising:
the first infrared sensors and the second infrared sensors are arranged on the first frame or the second frame along the horizontal direction;
the main control unit is further configured to: acquiring first sensing information of the first infrared sensor and second sensing information of the second infrared sensor, respectively recording acquisition times of the first sensing signal and the second sensing information, determining that the passing direction of a person is a first direction when the acquisition time of the first sensing signal is earlier than the acquisition time of the second sensing signal and the acquisition time of the first detection signal is earlier than the acquisition time of the second detection signal, and determining that the passing direction of the person is a second direction opposite to the first direction when the acquisition time of the first sensing signal is later than the acquisition time of the second sensing signal and the acquisition time of the first detection signal is later than the acquisition time of the second detection signal.
4. The nuclear power plant gamma ray radioactive contamination monitoring system of claim 1, wherein the master control unit is further configured to:
and when the first detection signal is acquired and the second detection signal is acquired within a set time length, counting the acquisition times, and obtaining the personnel passing times based on the acquisition times.
5. The system for monitoring gamma-ray radioactive contamination of nuclear power plants of claim 1, wherein the gamma-ray detectors respectively arranged in parallel in the vertical direction include a first area detector arranged near the top of the radiation monitoring passage door, a second area detection area arranged near the bottom of the radiation monitoring passage door, and a third area detector arranged between the first area detector and the second area detector;
the main control unit is further configured to:
based on the first detection signal and the second detection signal, detection signals of the first area detector, the second area detector and the third area detector are respectively extracted, ray monitoring values of human body areas respectively corresponding to different area detectors are obtained, based on the ray monitoring values, the human body area corresponding to the maximum ray monitoring value is determined, and prompt information is sent.
6. The nuclear power plant gamma ray radioactive contamination monitoring system of claim 1, wherein the master control unit is further configured to:
acquiring a ray counting rate of unit time based on the first detection signal and the second detection signal; and averaging the ray counting rate of each unit time in the set time length to be used as the background ray counting rate.
7. The nuclear power plant gamma ray radioactive contamination monitoring system of claim 1, wherein the radiation monitoring access door further comprises:
the third frame is connected with the bottom end of the first frame and the bottom end of the second frame, and the fourth frame is connected with the top end of the first frame and the top end of the second frame;
and the third frame and the fourth frame are provided with a set number of gamma-ray detectors.
8. The nuclear power plant gamma ray radioactive contamination monitoring system of claim 7,
the third frame is embedded in a groove in the ground, and the surface of the third frame facing the fourth frame is flush with the ground.
9. The nuclear power plant gamma ray radioactive contamination monitoring system of claim 1, further comprising:
the alarm device is connected with the main control unit and is used for executing the sending, responding or releasing operation of alarm information;
the ray monitoring access door is arranged at an outlet and/or an inlet of a nuclear facility factory area, and the alarm device is arranged in a guard room.
10. The nuclear power plant gamma ray radioactive contamination monitoring system of claim 1,
the gamma-ray detectors arranged in parallel on the opposite surfaces of the first frame and the second frame are staggered in position; alternatively, the first and second electrodes may be,
the gamma-ray detectors arranged in parallel on the opposite surfaces of the first frame and the second frame are flush with each other.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910954293.XA CN110749914B (en) | 2019-10-09 | 2019-10-09 | Nuclear power station gamma-ray radioactive pollution monitoring system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910954293.XA CN110749914B (en) | 2019-10-09 | 2019-10-09 | Nuclear power station gamma-ray radioactive pollution monitoring system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110749914A CN110749914A (en) | 2020-02-04 |
| CN110749914B true CN110749914B (en) | 2021-12-31 |
Family
ID=69277780
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910954293.XA Active CN110749914B (en) | 2019-10-09 | 2019-10-09 | Nuclear power station gamma-ray radioactive pollution monitoring system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110749914B (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112530140B (en) * | 2020-12-02 | 2022-05-13 | 中国兵器装备集团自动化研究所 | Joint alarm and pollution area division method based on adjacent position relation of detectors |
| CN113296142B (en) * | 2021-05-21 | 2023-01-17 | 山西中辐核仪器有限责任公司 | Conveyer belt type safety helmet pollution monitor |
| CN114994733B (en) * | 2022-07-20 | 2022-11-08 | 山西中辐核仪器有限责任公司 | Radiation monitoring method, device and system based on radiation monitor |
Family Cites Families (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3670164A (en) * | 1970-08-18 | 1972-06-13 | Atomic Energy Commission | Personnel plutonium monitor |
| EP0060574A1 (en) * | 1981-03-13 | 1982-09-22 | UNC Nuclear Industries, Inc. | Portal type personnel radiation monitor |
| CN100420937C (en) * | 2003-09-18 | 2008-09-24 | 清华大学 | Method for monitoring positioning of vehicle radioactive substance and its device |
| RU2384865C1 (en) * | 2008-12-09 | 2010-03-20 | Открытое акционерное общество "Научно-технический центр РАТЭК" | Method for radiation monitoring moving objects and portal radiation monitor for realising said method |
| CN103632406A (en) * | 2013-12-11 | 2014-03-12 | 周卫荣 | Intelligent attendance system |
| CN103817086B (en) * | 2014-03-18 | 2017-03-01 | 威海北洋电气集团股份有限公司 | Lane device and baggage sorting method are controlled in baggage sorting footpath |
| CN205539503U (en) * | 2016-03-07 | 2016-08-31 | 北京中科核安科技有限公司 | Quick response monitors passageway formula pedestrian radioactivity monitoring system entirely |
| CN206906588U (en) * | 2017-05-10 | 2018-01-19 | 上海新漫传感技术研究发展有限公司 | The panel detector structure of pedestrian's nuclear radiation monitoring system |
| CN208580211U (en) * | 2018-06-25 | 2019-03-05 | 上海新漫传感技术研究发展有限公司 | Whole-body γ portal monitor panel detector structure |
-
2019
- 2019-10-09 CN CN201910954293.XA patent/CN110749914B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN110749914A (en) | 2020-02-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN110749914B (en) | Nuclear power station gamma-ray radioactive pollution monitoring system | |
| CN103913762B (en) | A kind of passage radioactive material quality detection supervising device and detection method | |
| KR101415859B1 (en) | Apparatus and method for detection of radiation | |
| CN111798643B (en) | Novel global critical accident alarm method and system | |
| CN101210894B (en) | System and method for simultaneously carrying out radiation imaging inspection and radioactive matter monitoring | |
| US3670164A (en) | Personnel plutonium monitor | |
| US20110261650A1 (en) | Method for the radiation monitoring of moving objects and a radiation portal monitor for carrying out said method | |
| JP6072977B2 (en) | Radiation monitor | |
| CN111337968A (en) | Radiation monitoring system | |
| CN101855574A (en) | Device and method for monitoring the radioactive contamination of a user | |
| KR101145859B1 (en) | A whole body counter for discrimination between internal and external radioactive contamination | |
| EP3839914A1 (en) | Identification of an anomaly on a detector | |
| CN104459755A (en) | Vehicle radioactive substance detection and positioning device and method | |
| JP4225499B2 (en) | Fire detection equipment | |
| CN207181705U (en) | A kind of nuclear matter pedestrian monitoring system for keeping sensitivity uniformity | |
| NL2025257B1 (en) | Vehicle monitoring system and method of monitoring vehicles | |
| RU2293999C1 (en) | Method of detection and measurement of weak flows of ionizing radiations | |
| CN201196636Y (en) | Integration system used for active material detection and X ray radiation imaging | |
| CN216848169U (en) | Nuclear medicine workshop radiation and security protection integration monitoring system | |
| JP4086189B2 (en) | Radiation monitoring post | |
| Ely et al. | Lithium loaded glass fiber neutron detector tests | |
| CN102565097B (en) | Integration system for radioactive substance detection and X-ray radiation imaging | |
| Sonck et al. | TELERAD: the radiological surveillance network and early warning system in Belgium | |
| JP2001281337A (en) | Radiation detector and body surface contamination monitor | |
| Brunskill et al. | The detection and measurement of plutonium airborne contamination in major plutonium facilities |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |