CN112327344A - Monitoring terminal and measuring method for dose equivalent rate and radioactivity activity - Google Patents
Monitoring terminal and measuring method for dose equivalent rate and radioactivity activity Download PDFInfo
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Abstract
The invention discloses a terminal for monitoring dose equivalent rate and radioactivity activity, which comprises: a detection unit and a control unit; the detection unit is in bidirectional electric connection with the control unit; the detection unit comprises a double-path detector and an analysis calibrator; the two-way detector includes: the device comprises a photomultiplier and NaI crystals, wherein the NaI crystals are arranged on two sides of the photomultiplier; the photomultiplier is used for receiving optical signals generated when gamma rays penetrate through the NaI crystals on the two sides and performing photoelectric conversion on the optical signals to obtain electric signals; the analysis scaler is used for performing coincidence counting and comparative analysis on the electric signals acquired by the photomultiplier; the control unit comprises a control chip. Also disclosed is a method for measuring dose equivalent rate and radioactivity, comprising: s1, obtaining the dose equivalent rate of gamma rays emitted by a radioactive source to be detected through NaI crystals
S2, according to the dose equivalent rate
The value of the activity a is calculated. The invention effectively solves the problem that the radioactivity of the body surface of the patient cannot be monitored in the prior art.
Description
Technical Field
The invention relates to the technical field of nuclear medicine, in particular to a terminal and a method for monitoring dose equivalent rate and radioactivity.
Background
Using large doses131I removal and treatment of residual tissue and metastases after thyroid tumor (DTC) surgery have achieved widespread use in clinical therapy. The patient is taking radioactivity131After the radiation treatment, a strong radiation field is formed in the body, so that the patient becomes a living mobile radiation source, and radiation damage is caused to the surrounding environment and people. Therefore, most patients are treated in isolated hospitalizations in special wards of hospitals to ensure the health and safety of patients in close contact with the patients (such as medical staff and family members). For patients treated, the patient may be isolated if the activity in the body, which meets national regulations, falls below 400MBq or below the national public limit of 2.5 μ Sv/h at 1m around, and an individualized absorbed dose calculation is performed. Meanwhile, the basic standard (GB18871-2002) for ionizing radiation protection and radiation source safety specifically stipulates that the public irradiation dose constraint limit value is within the range of 0.1-0.3 mSv/a (100-300 mu Sv/a).
At present, against thyroid cancer131I superficial radiation of the patient for treatmentThere are relatively few systems for activity monitoring. The attending physician of the patient will generally follow131Empirical formula of I metabolism in humans calculates the approximate time of discharge of patients, but since each patient pair131The absorption and metabolism ability of I are different, and some attending physicians usually increase the basic treatment dosage of patients properly in order to obtain better treatment effect in the clinical treatment process, which may cause the patients to have a certain dose of radioactivity remaining in the bodies at the time of discharge and cause radiation damage to people contacting the surroundings.
Therefore, in order to really ensure the health and safety of the patient who is in close contact with the patient and guide medical care personnel and family members of the patient to do personal protection, how to provide a medicine suitable for thyroid cancer131I monitoring terminal and measuring method for dose equivalent rate and radioactivity of treated patients is a problem to be solved by the technical personnel in the field.
Disclosure of Invention
In view of this, the invention provides a terminal and a method for monitoring dose equivalent rate and radioactivity, which effectively solve the problem that radioactivity on the surface of a patient cannot be monitored in the prior art.
In order to achieve the purpose, the invention adopts the following technical scheme:
a terminal for monitoring dose equivalent rate and radioactivity activity is wirelessly connected with an upper computer, and comprises: a detection unit and a control unit; the detection unit is in bidirectional electric connection with the control unit;
the detection unit comprises a double-path detector and an analysis calibrator;
the two-way detector includes: the device comprises a photomultiplier and NaI crystals, wherein the NaI crystals are arranged on two sides of the photomultiplier;
the photomultiplier is used for receiving optical signals generated when gamma rays penetrate through NaI crystals on two sides, and performing photoelectric conversion on the optical signals to obtain electric signals;
the analysis scaler is used for performing coincidence counting and comparative analysis on the electric signals acquired by the photomultiplier;
the control unit comprises a control chip which calculates the values of dose equivalent rate and radioactivity according to the electric signals generated by the analysis scaler.
Preferably, the detection unit further includes: a voltage divider and an amplifying circuit;
the voltage divider is electrically connected with the photomultiplier and is used for supplying power to the photomultiplier;
the amplifying circuit is respectively and electrically connected with the analysis scaler and the control unit; the amplifying circuit is used for amplifying the electric signal and sending the amplified electric signal to the control unit.
Preferably, the control unit further comprises an analog-to-digital conversion circuit, a memory and a wireless communication module; the analog-to-digital conversion circuit, the memory and the wireless communication module are all electrically connected with the control chip;
the analog-to-digital conversion circuit is used for receiving the electric signal detected by the detection unit and converting the electric signal into the digital signal;
the control chip is used for receiving the digital signals converted by the analog-to-digital conversion circuit, processing the digital signals and calculating to obtain the dose equivalent rate and the radioactivity value;
the memory is used for caching the collected historical data;
the wireless communication module is used for transmitting data with the upper computer.
Preferably, the monitoring and alarming device further comprises a monitoring and alarming unit, wherein the monitoring and alarming unit comprises an infrared sensor, a camera and an audible and visual alarm; the infrared sensor, the camera and the audible and visual alarm are all electrically connected with the control chip;
the infrared sensor is used for detecting whether a human body to be detected exists in a detection range, and if the human body to be detected exists, the monitoring of the dose equivalent rate and the radioactivity is started through the control chip;
the camera is used for collecting the portrait of the human body to be detected after the infrared sensor detects the human body to be detected and sending the collected portrait data information to the upper computer;
the audible and visual alarm is used for acquiring alarm information sent by the control chip, sending out buzzing sound and controlling an alarm lamp in the alarm to flicker; and the control chip judges whether the monitored values of the dose equivalent rate and the radioactivity activity exceed threshold values or not, and sends alarm information to the audible and visual alarm if the monitored values exceed the threshold values.
Preferably, the device further comprises a display unit, wherein the display unit is electrically connected with the control unit;
and the display unit is used for receiving and displaying the values of the dose equivalent rate and the radioactivity calculated by the control chip.
Preferably, the charging system further comprises a power supply unit, wherein the power supply unit comprises a power switch, a 220V power supply, a lithium battery and a charging module;
the power switch is respectively and electrically connected with the control chip, the 220V power supply, the lithium battery and the charging module and is used for controlling the on-off of the power supply of the monitoring terminal;
the 220V power supply and the lithium battery are respectively used for supplying power to the monitoring terminal, and the charging module is used for charging the lithium battery.
A method for measuring dose equivalent rate and radioactivity specifically comprises the following steps:
s1, obtaining the dose equivalent rate of gamma rays emitted by a radioactive source to be detected through NaI crystals
S2, according to the dose equivalent rate
The value of radioactivity A was calculated as: radioactivity A and rate of irradiation
The relationship between them is:
in the formula: gamma irradiation rate constant, R is the distance between the radioactive source to be measured and the detector;
according to dose equivalent rate
And absorption dose rate
And rate of irradiation
The relationship between the activity A and the dose equivalent rate
The relationship between them, the value of the activity a is obtained:
preferably, the specific step of S1 includes: gamma rays generated by a radioactive source to be detected penetrate through the NaI crystal to generate optical signals, and the optical signals are subjected to photoelectric conversion to obtain electric signals; and amplifying the electric signal, and converting the amplified electric signal into a digital signal.
Preferably, the specific contents of S2 include:
absorption dose rate
And rate of irradiation
The following relationships exist:
absorption dose rate
Dose equivalent rate
The following relationships exist:
wherein: n is the product of all other correction factors, ICRP specifies N1; q is a quality factor, Q is 1 in the external irradiation, and equation (3) is further simplified as:
thus the radioactivity A is:
according to the technical scheme, compared with the prior art, the monitoring terminal and the measuring method of the dose equivalent rate and the radioactivity activity are provided, the monitoring terminal adopts a double-path detector, background interference can be eliminated through coincidence counting of the double-path detector, the dose equivalent rate generated by a radioactive source (namely a patient) to be detected can be effectively monitored, the radioactivity activity is calculated through a control chip according to the monitored dose equivalent rate, the problem that direct monitoring and calculation on the body surface radioactivity of the patient are lacked in the prior art is effectively solved, the working efficiency of body surface radioactivity monitoring is improved, the value of the radioactivity activity can be more accurately obtained, the situation that the patient is subjected to secondary damage after being discharged from a hospital is avoided, and the safety is improved; the method for monitoring the radioactivity has the advantages of simple calculation process and strong practicability.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the provided drawings without creative efforts.
Fig. 1 is a schematic diagram illustrating an entity structure of a terminal for monitoring dose equivalent rate and radioactivity provided in the present invention;
fig. 2 is a schematic diagram of a frame structure of a terminal for monitoring dose equivalent rate and radioactivity provided in the present invention;
FIG. 3 is a flowchart illustrating a process of a terminal for monitoring dose equivalent rate and radioactivity provided in the present invention;
the monitoring alarm device comprises a monitoring alarm unit A1, an infrared sensor A11, an audible and visual alarm A13, a control unit A2, an analog-to-digital conversion circuit A21, a control chip A22, a memory A23, a wireless module A24, a detection unit A3, a NaI crystal A31, a photomultiplier A32, an amplification circuit A33, an analysis scaler A34, a voltage divider A35, a power supply unit A4, a power switch A41, a 220V power supply A42, a lithium battery A43, a charging module A44, a display unit A5 and a base A6.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
The embodiment of the invention discloses a dose equivalent rate and radioactivity monitoring terminal which is wirelessly connected with an upper computer, and in the embodiment, as shown in fig. 1, the monitoring terminal is designed in a square column structure, a base A6 is in a disc shape and sequentially comprises a monitoring alarm unit A1, a control unit A2, a detection unit A3, a power supply unit A4 and other partial modules from top to bottom, a display unit A5 is installed on the outer side of the control unit A2, and the frame relationship is shown in fig. 2.
For the detection unit A3 and the control unit a 2:
the detection unit A3 is in bidirectional electric connection with the control unit A2; the detection unit A3 comprises a two-way detector and an analysis scaler A34;
the two-way detector includes: the device comprises a photomultiplier A32 and a NaI crystal A31, wherein the NaI crystal A31 is arranged on each of two sides of the photomultiplier A32;
the photomultiplier A32 is used for receiving optical signals generated when gamma rays penetrate through NaI crystals A31 on two sides, and performing photoelectric conversion on the optical signals to obtain electric signals;
the analysis scaler A34 is used for performing coincidence counting and comparative analysis on the electric signals acquired by the photomultiplier A32;
the control unit a2 includes a control chip a22, and the control chip a22 calculates the dose equivalent rate and the value of radioactivity from the electric signal generated by the analysis scaler a 34.
In order to further implement the above technical solution, the detecting unit a3 may further include: a voltage divider a35 and an amplifying circuit a 33;
the voltage divider A35 is electrically connected with the photomultiplier A32, and the voltage divider A35 is used for supplying power to the photomultiplier A32;
the amplifying circuit A33 is respectively and electrically connected with the analysis scaler A34 and the control unit; the amplifier circuit a33 is used to amplify the electrical signal and send the amplified electrical signal to the control unit.
In order to further implement the above technical solution, the control unit further includes an analog-to-digital conversion circuit a21, a memory a23, and a wireless communication module; the analog-to-digital conversion circuit A21, the memory A23 and the wireless communication module are all electrically connected with the control chip A22;
the analog-to-digital conversion circuit A21 is used for receiving the electric signal detected by the detection unit A3 and converting the electric signal into a digital signal;
the control chip A22 is used for receiving the digital signals converted by the analog-to-digital conversion circuit A21, processing the digital signals and calculating to obtain the dose equivalent rate and the radioactivity value;
the memory A23 is used for caching the collected historical data;
the wireless communication module is used for transmitting data with the upper computer.
In order to further implement the technical scheme, the display unit A5 is electrically connected with the control unit A2;
the display unit A5 is used for receiving and displaying the values of the dose equivalent rate and the radioactivity calculated by the control chip A22.
It needs to be further explained that:
the control unit A2 is located below the monitoring alarm unit A1 and is the core of monitoring terminal control and data storage, the display unit A5 includes a 5-inch longitudinally arranged LED display screen right in front of the outside, the displayed content is as shown in FIG. 3, the numerical values of dose equivalent rate and radioactivity activity and state indication are displayed in two rows, the state indication strip sequentially divides three areas of a safety area (green block mark), a pre-warning area (yellow block mark) and a danger area (red block mark) from left to right, color gradients are adopted among different color blocks for transition, the display interval of the state indication strip is [ 0-maximum range ], a black inverted triangle is a data indicator of the state indication strip, and the dose level or activity level of the current numerical value is visually displayed. In the control unit a2, the control chip a22 is a control center for data acquisition, data processing and transmission and task scheduling of the monitoring terminal, and is responsible for transmitting commands and signals with other unit modules; the memory A23 is mainly used as a data storage module of the monitoring terminal, stores temporary collected data and part of historical data, and organizes and manages the data in a first-in first-out queue mode, namely, newly-entered data covers earlier-stored data in a rolling covering mode; the wireless module A24 can be used for packaging and sending data to an upper computer through a Wifi network for processing.
The detection unit A3 is located in the middle of the monitoring terminal, a double-path NaI crystal A31 is arranged in the detection unit, a photomultiplier A32 is located between the two NaI crystals A31, receives optical signals generated when gamma rays penetrate through the NaI crystals A31 on two sides, performs photoelectric conversion on the optical signals, performs operation processing on double-path analog electric signals through an analysis scaler A34 to obtain standard pulse signals of an upper path and a lower path, filters and eliminates natural background signals through coincidence calculation and comparison analysis, and sends the natural background signals to the data processing unit for subsequent processing after judging that data signals higher than the background are obtained. The double-path signal coincidence counting is that the pulse generated by incident particles at the top end of the detector is used as a gate pulse, the other end of the detector is used as a signal pulse, the two pulses are recorded only when arriving within the resolution time of a coincidence circuit, and the background signal and the signal of an irrelevant event are randomly distributed in time, so that the coincidence condition is not met and the background signal is not recorded, namely the interference of the background can be eliminated by the coincidence counting method of the double-path detector. The amplifying circuit a33 mainly performs operational amplification processing on the weak pulse signal of the mature path detector. The analog-to-digital conversion circuit a21 performs data conversion between analog data (voltage value) and digital signals (dose count).
In order to further implement the technical scheme, the monitoring alarm unit A1 comprises an infrared sensor A11, a camera and an audible and visual alarm A13; the infrared sensor A11, the camera and the audible and visual alarm A13 are all electrically connected with the control chip A22;
the infrared sensor A11 is used for detecting whether a human body to be detected exists in the detection range, and if the human body to be detected exists, the monitoring of the dose equivalent rate and the radioactivity is started through the control chip A22;
the camera is used for acquiring a portrait of a human body to be detected after the infrared sensor A11 detects the human body to be detected and sending acquired portrait data information to the upper computer;
the audible and visual alarm A13 is used for acquiring alarm information sent by the control chip A22, sending out buzzer sound and controlling an alarm lamp in the alarm to flash; the control chip A22 judges whether the monitored values of dose equivalent rate and radioactivity exceed threshold values, and if the monitored values exceed the threshold values, alarm information is sent to an audible and visual alarm A13.
It needs to be further explained that:
the monitoring alarm unit A1 is located at the top of the monitoring terminal, an infrared sensor A11 and a camera A12 are arranged right in front of the monitoring alarm unit A1, and an audible and visual alarm A13 with functions of buzzing and red and blue light changing and flashing is arranged inside the monitoring alarm unit A13. The infrared detector can detect whether a human body exists in front, and awaken or start the monitoring terminal to measure the dose equivalent rate (hereinafter referred to as dose rate) and the radioactivity (hereinafter referred to as activity) of the person entering the detection range (1 m); the camera can collect images of the patient so as to verify the identity of the patient and generate a detection report; the audible and visual alarm A13 triggers an alarm when the monitored value exceeds a set threshold value, sends out a buzzer sound and alternately lights up red and blue alarm lamps.
In order to further implement the above technical solution, the power supply unit a4 includes a power switch a41, a 220V power supply a42, a lithium battery a43, and a charging module a 44;
the power switch A41 is respectively electrically connected with the control chip A22, the 220V power supply A42, the lithium battery A43 and the charging module A44 and is used for controlling the on-off of the power supply of the monitoring terminal;
the 220V power supply A42 and the lithium battery A43 are respectively used for supplying power to the monitoring terminal, and the charging module A44 is used for charging the lithium battery A43.
It needs to be further explained that:
the power supply unit A4 is located at the bottom of the monitoring terminal and comprises a power switch A41, a 220V power supply A42, a lithium battery A43 and a charging module A44. The power supply unit A4 is a module for monitoring the whole power supply of the terminal, supports dual power supply of 220V and a built-in lithium battery A43, and can charge the lithium battery A43 through the charging module A44 when the 220V power supply A42 is accessed, so that the long-term stable operation of the monitoring terminal is ensured.
The working principle of the monitoring terminal is as follows:
firstly, a 220V power supply A42 of the monitoring terminal is inserted into a 220V power supply socket, a built-in lithium battery A43 can be charged simultaneously, and a charging module A44 is automatically closed if the electric quantity of the built-in lithium battery A43 is saturated; the power can also be supplied by directly adopting the built-in lithium battery A43 under the condition that the electric quantity of the built-in lithium battery A43 is sufficient; the power switch A41 is turned on, the outer ring indicator light of the power switch A41 can turn green, the fact that the power supply unit A4 works normally is proved, if the outer ring indicator light is displayed to be red, the fact that the power supply unit A4 has faults and needs to be overhauled is proved, and the outer ring indicator light is in an off state when the power switch A41 is not turned on.
The control chip a22 of the monitoring terminal is started after being powered on, and controls each unit module to start working, such as: and the display screen is lightened, the screen display content is initialized, the functions of all modules of the detection unit A3 are started, the initial setting of the operation parameters is carried out, and the infrared sensor A11 module of the sound-light alarm unit is started.
When the infrared sensor A11 module detects that a human body enters a detection range, a camera is started to capture the face of the human body, the image is stored in the memory A23, the detection module is activated at the same time, the dual-path NaI crystal A31 receives gamma-ray photons released by the patient, the photons are converted into electrons through the photoelectric conversion function of the photomultiplier A32, the electrons are analyzed, calibrated and coincided with the count after being amplified, the electrons are converted into identifiable data through the analog-to-digital conversion circuit A21, the data are collected, processed and stored by the control chip A22 for comprehensive management, the collected data are temporarily stored in the memory A23 and pushed to the display screen by the control chip A22 for displaying the dose equivalent rate and the radioactivity, if the collected data exceed the alarm limit, the control chip A22 sends an alarm instruction to the acousto-optic alarm unit, the acousto-optic alarm unit sends out a buzz and triggers the alternate flashing of a red-blue alarm lamp after receiving the instruction, when the data is reduced below the alarm threshold value, the monitoring terminal automatically releases the sound-light alarm; if the infrared sensor A11 does not detect a human body, the monitoring terminal is in a low-power-consumption sleep state.
Finally, all the acquired data are uniformly retrieved from the memory A23 by the control chip A22, the data are packaged according to the agreed data format, the data pushing frequency is set according to the agreed time for data aging and the total amount of the data, the data are generally sent by the wireless module A24 once every half second, if the data are not sent successfully, the data are tried to be connected with the upper computer again and sent again, and after three failures, the data are sent at intervals of a period of time (such as after 3 minutes).
The embodiment also discloses a method for measuring dose equivalent rate and radioactivity, which specifically comprises the following steps:
s1, acquiring the dose equivalent rate of gamma rays emitted by a radioactive source to be detected through a NaI crystal A31
S2, according to the dose equivalent rate
The value of radioactivity A was calculated as: radioactivity A and rate of irradiation
The relationship between them is:
in the formula: gamma irradiation rate constant, R is the distance between the radioactive source to be measured and the detector;
according to dose equivalent rate
And absorption dose rate
And rate of irradiation
The relationship between the activity A and the dose equivalent rate
The relationship between them, the value of the activity a is obtained:
in order to further implement the above technical solution, the specific step of S1 includes: gamma rays generated by a radioactive source to be detected penetrate through the NaI crystal A31 to generate optical signals, and the optical signals are subjected to photoelectric conversion to obtain electric signals; and amplifying the electric signal, and converting the amplified electric signal into a digital signal.
In order to further implement the above technical solution, the specific content of S2 includes:
absorption dose rate
And rate of irradiation
The following relationships exist:
absorption dose rate
Dose equivalent rate
The following relationships exist:
wherein: n is the product of all other correction factors, ICRP specifies N1; q is a quality factor, Q is 1 in the external irradiation, and equation (3) is further simplified as:
thus the radioactivity A is:
it needs to be further explained that:
due to the fact that131I is generally accumulated in humansAround the thyroid gland of the body, and thus will be acceptable over a range of distances131I, treating a patient with thyroid cancer as a point source, wherein the calculation formula of the irradiation rate of the point source is formula (1);
in general, the dose equivalent rate of a patient can be obtained directly by measurement, but the radioactivity is not easily measured, and thus the radioactivity a can be obtained by reverse derivation of equations (1) - (4). If Γ is 2.56 × 10, depending on the distance R between the patient and the detector, 1m-18C·m2Kg, equation (5) can be further simplified as:
the embodiments in the present description are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same and similar parts among the embodiments are referred to each other. The device disclosed by the embodiment corresponds to the method disclosed by the embodiment, so that the description is simple, and the relevant points can be referred to the method part for description.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
Claims (9)
1. The utility model provides a dose equivalent rate and radioactivity activity's monitor terminal, with host computer wireless connection, its characterized in that includes: a detection unit and a control unit; the detection unit is in bidirectional electric connection with the control unit;
the detection unit comprises a double-path detector and an analysis calibrator;
the two-way detector includes: the device comprises a photomultiplier and NaI crystals, wherein the NaI crystals are arranged on two sides of the photomultiplier;
the photomultiplier is used for receiving optical signals generated when gamma rays penetrate through NaI crystals on two sides, and performing photoelectric conversion on the optical signals to obtain electric signals;
the analysis scaler is used for performing coincidence counting and comparative analysis on the electric signals acquired by the photomultiplier;
the control unit comprises a control chip which calculates the values of dose equivalent rate and radioactivity according to the electric signals generated by the analysis scaler.
2. The terminal for monitoring dose equivalent rate and radioactivity according to claim 1, wherein the detecting unit further comprises: a voltage divider and an amplifying circuit;
the voltage divider is electrically connected with the photomultiplier and is used for supplying power to the photomultiplier;
the amplifying circuit is respectively and electrically connected with the analysis scaler and the control unit; the amplifying circuit is used for amplifying the electric signal and sending the amplified electric signal to the control unit.
3. The terminal of claim 1, wherein the control unit further comprises an analog-to-digital conversion circuit, a memory, and a wireless communication module; the analog-to-digital conversion circuit, the memory and the wireless communication module are all electrically connected with the control chip;
the analog-to-digital conversion circuit is used for receiving the electric signal detected by the detection unit and converting the electric signal into the digital signal;
the control chip is used for receiving the digital signals converted by the analog-to-digital conversion circuit, processing the digital signals and calculating to obtain the dose equivalent rate and the radioactivity value;
the memory is used for caching the collected historical data;
the wireless communication module is used for transmitting data with the upper computer.
4. The terminal for monitoring dose equivalent rate and radioactivity according to claim 1, further comprising a monitoring alarm unit, wherein the monitoring alarm unit comprises an infrared sensor, a camera and an audible and visual alarm; the infrared sensor, the camera and the audible and visual alarm are all electrically connected with the control chip;
the infrared sensor is used for detecting whether a human body to be detected exists in a detection range, and if the human body to be detected exists, the monitoring of the dose equivalent rate and the radioactivity is started through the control chip;
the camera is used for collecting the portrait of the human body to be detected after the infrared sensor detects the human body to be detected and sending the collected portrait data information to the upper computer;
the audible and visual alarm is used for acquiring alarm information sent by the control chip, sending out buzzing sound and controlling an alarm lamp in the alarm to flicker; and the control chip judges whether the monitored values of the dose equivalent rate and the radioactivity activity exceed threshold values or not, and sends alarm information to the audible and visual alarm if the monitored values exceed the threshold values.
5. The terminal for monitoring dose equivalent rate and radioactivity according to claim 1, further comprising a display unit, wherein the display unit is electrically connected to the control unit;
and the display unit is used for receiving and displaying the values of the dose equivalent rate and the radioactivity calculated by the control chip.
6. The terminal for monitoring dose equivalent rate and radioactivity according to claim 1, further comprising a power supply unit, wherein the power supply unit comprises a power switch, a 220V power supply, a lithium battery and a charging module;
the power switch is respectively and electrically connected with the control chip, the 220V power supply, the lithium battery and the charging module and is used for controlling the on-off of the power supply of the monitoring terminal;
the 220V power supply and the lithium battery are respectively used for supplying power to the monitoring terminal, and the charging module is used for charging the lithium battery.
7. A method for measuring dose equivalent rate and radioactivity is characterized by comprising the following steps:
s1, obtaining the dose equivalent rate of gamma rays emitted by a radioactive source to be detected through NaI crystals
S2, according to the dose equivalent rate
The value of radioactivity A was calculated as: radioactivity A and rate of irradiation
The relationship between them is:
in the formula: gamma irradiation rate constant, R is the distance between the radioactive source to be measured and the detector;
according to dose equivalent rate
And absorption dose rate
And rate of irradiation
The relationship between the activity A and the dose equivalent rate
The relationship between them, the value of the activity a is obtained:
8. the method as claimed in claim 7, wherein the step of S1 comprises: gamma rays generated by a radioactive source to be detected penetrate through the NaI crystal to generate optical signals, and the optical signals are subjected to photoelectric conversion to obtain electric signals; and amplifying the electric signal, and converting the amplified electric signal into a digital signal.
9. The method of claim 7, wherein the step of S2 comprises:
absorption dose rate
And rate of irradiation
The following relationships exist:
absorption dose rate
Dose equivalent rate
The following relationships exist:
wherein: n is the product of all other correction factors, ICRP specifies N1; q is a quality factor, Q is 1 in the external irradiation, and equation (3) is further simplified as:
thus the radioactivity A is:
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| CN104730563A (en) * | 2013-12-24 | 2015-06-24 | 上海新漫传感技术研究发展有限公司 | Passage type personnel radioactivity monitor |
| CN110824541A (en) * | 2019-11-14 | 2020-02-21 | 南华大学 | 18F digital coincidence monitoring device and monitoring method |
| CN214201791U (en) * | 2020-11-25 | 2021-09-14 | 黑龙江省科学院技术物理研究所 | Monitoring terminal for dose equivalent rate and radioactivity activity |
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| CN104730563A (en) * | 2013-12-24 | 2015-06-24 | 上海新漫传感技术研究发展有限公司 | Passage type personnel radioactivity monitor |
| CN110824541A (en) * | 2019-11-14 | 2020-02-21 | 南华大学 | 18F digital coincidence monitoring device and monitoring method |
| CN214201791U (en) * | 2020-11-25 | 2021-09-14 | 黑龙江省科学院技术物理研究所 | Monitoring terminal for dose equivalent rate and radioactivity activity |
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