CN110456402B - Radiation dose detection method and device - Google Patents
Radiation dose detection method and device Download PDFInfo
- Publication number
- CN110456402B CN110456402B CN201910663174.9A CN201910663174A CN110456402B CN 110456402 B CN110456402 B CN 110456402B CN 201910663174 A CN201910663174 A CN 201910663174A CN 110456402 B CN110456402 B CN 110456402B
- Authority
- CN
- China
- Prior art keywords
- radiation
- energy
- unit time
- detection
- radiation dose
- 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
- G01T1/15—Instruments in which pulses generated by a radiation detector are integrated, e.g. by a diode pump circuit
Landscapes
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Abstract
The disclosure relates to a radiation dose detection method and a radiation dose detection device, which belong to the field of nuclear radiation detection and can accurately detect the dose of radioactive radiation. A radiation dose detection method comprising: detecting the energy of a single radiation particle by using an electronic pulse signal output by the radiation particle detector; counting the number of the single radiation particles in unit time; calculating the radiation dose per unit time based on the counted number per unit time and the energy of each corresponding radiation particle.
Description
Technical Field
The present disclosure relates to the field of nuclear radiation detection, and in particular, to a radiation dose detection method and apparatus.
Background
The existing radioactive radiation dose detection scheme is that the radiation dose is obtained by collecting after integrating electronic pulses in unit time and calculating. However, after the pulse signal is obtained after the integration, the radiation dose is estimated by a model, and thus the radiation dose cannot be accurately detected.
Disclosure of Invention
An object of the present disclosure is to provide a radiation dose detection method and apparatus capable of accurately detecting a dose of radioactive radiation.
According to a first embodiment of the present disclosure, there is provided a radiation dose detection method including: detecting the energy of a single radiation particle by using an electronic pulse signal output by the radiation particle detector; counting the number of the single radiation particles in unit time; calculating the radiation dose per unit time based on the counted number per unit time and the energy of each corresponding radiation particle.
Optionally, the detecting the energy of the single radiation particle by using the electronic pulse signal output by the radiation particle detector is implemented by at least one of a low power consumption detection mode and a parallel acquisition detection mode: (1) in the low power detection mode: detecting the amplitude of the electronic pulse signal; collecting the amplitude of the electronic pulse signal as the energy of the single radiation particle under the condition that the detected amplitude exceeds a preset pulse threshold; (2) in the parallel acquisition detection mode: and continuously acquiring the electronic pulse signals in parallel to obtain an electronic pulse envelope, and calculating the area of the electronic pulse envelope as the energy of the single radiation particle.
Optionally, in the low power consumption detection mode, the counting the number of the single radiation particles in a unit time includes: and counting the number of the amplitude values acquired in the unit time as the number of the single radiation particles in the unit time.
Optionally, in the parallel acquisition detection mode, the counting the number of the single radiation particles in a unit time includes: and counting the number of the electronic pulse envelopes collected in the unit time as the number of the single radiation particles in the unit time.
Optionally, the method further comprises: comparing the calculated radiation dose with a preset radiation dose threshold; and switching between the low power consumption detection mode and the parallel acquisition detection mode based on the comparison result.
Optionally, the preset radiation dose threshold is a preset radiation dose threshold based on safety experience or a natural environment background radiation dose.
Optionally, the method further comprises: sending a gain adjustment instruction to the radiation particle detector based on the distribution of the detected energy, wherein the gain adjustment instruction causes the radiation particle detector to adjust its output gain.
According to a second embodiment of the present disclosure, there is provided a radiation dose detecting apparatus including: the energy detection module is used for detecting the energy of a single radiation particle by using the electronic pulse signal output by the radiation particle detector; and the microcontroller is used for counting the number of the single radiation particles in unit time and calculating the radiation dose in unit time based on the counted number in unit time and the energy of each corresponding radiation particle detected by the energy detection module.
Optionally, the energy detection module comprises at least one of a low power consumption energy detection sub-module and a parallel acquisition energy detection sub-module, wherein: the low-power-consumption energy detection submodule comprises a threshold detection circuit and a sample-and-hold circuit, wherein: the threshold detection circuit is used for detecting the amplitude of the electronic pulse signal, comparing the detected amplitude with a preset pulse threshold and sending a comparison result to the microcontroller, the sample-and-hold circuit is used for collecting and holding the amplitude of the electronic pulse signal, and the microcontroller is also used for processing the amplitude collected by the sample-and-hold circuit to obtain the energy of the single radiation particle when the comparison result shows that the detected amplitude exceeds the preset pulse threshold; the parallel acquisition energy detection submodule comprises a parallel acquisition channel, the parallel acquisition channel is used for continuously acquiring the electronic pulse signals in parallel and sending acquired data to the microcontroller, and the microcontroller is also used for obtaining an electronic pulse envelope based on the acquired data acquired by the parallel acquisition channel and calculating the area of the electronic pulse envelope to serve as the energy of the single radiation particle.
Optionally, in a case where the low-power-consumption energy detection submodule is active, the microcontroller counts the number of amplitude values acquired by the sample-and-hold circuit per unit time, as the number of single radiation particles per unit time.
Optionally, in a case where the parallel-acquisition energy detection submodule is in operation, the microcontroller counts the number of the electronic pulse envelopes obtained in the unit time as the number of the single radiation particles in the unit time.
Optionally, the microcontroller is further configured to: comparing the calculated radiation dose with a preset radiation dose threshold; and switching between the low-power energy detection submodule and the parallel acquisition energy detection submodule based on a comparison result.
Optionally, the preset radiation dose threshold is a preset radiation dose threshold based on safety experience or a natural environment background radiation dose.
Optionally, the microcontroller is further configured to: sending a gain adjustment instruction to the radiation particle detector based on the distribution of the detected energy, wherein the gain adjustment instruction causes the radiation particle detector to adjust its output gain.
Optionally, the low-power-consumption energy detection submodule further includes a reset circuit, configured to reset outputs of the threshold detection circuit and the sample-and-hold circuit after the microcontroller receives the amplitude value acquired by the sample-and-hold circuit.
Optionally, the reset circuit is further configured to reset the input of the sample-and-hold circuit after the microcontroller receives the amplitude value collected by the sample-and-hold circuit.
By adopting the technical scheme, the energy of the single radiation particle is detected by using the electronic pulse signal output by the radiation particle detector and the number of the single radiation particle in unit time is counted, so that the capability information of the single radiation particle can be well kept, the radiation particles captured by the radiation particle detector are completely collected in the radiation dose detection process and cannot be missed, and the accuracy of the radiation dose detection can be ensured by accurately detecting the energy and the number of the single radiation particle. Moreover, because single radiation particles are detected independently, the influence of noise accumulation in the existing time integration method can be avoided, natural background radiation interference is avoided, and low power consumption in a background detection state is realized.
Additional features and advantages of the disclosure will be set forth in the detailed description which follows.
Drawings
The accompanying drawings, which are included to provide a further understanding of the disclosure and are incorporated in and constitute a part of this specification, illustrate embodiments of the disclosure and together with the description serve to explain the disclosure without limiting the disclosure. In the drawings:
fig. 1 shows a flow chart of a radiation dose detection method according to an embodiment of the present disclosure.
Fig. 2 is a schematic block diagram of a radiation dose detection device according to an embodiment of the present disclosure.
Fig. 3 shows a further schematic block diagram of a radiation dose detection device according to an embodiment of the present disclosure.
Fig. 4 shows a circuit schematic of the low power energy detection submodule.
Detailed Description
The following detailed description of specific embodiments of the present disclosure is provided in connection with the accompanying drawings. It should be understood that the detailed description and specific examples, while indicating the present disclosure, are given by way of illustration and explanation only, not limitation.
The inventors of the present disclosure found that existing radiation dose detection schemes lose information on the ability of individual radiation particles after the integration process. Therefore, in order to be able to accurately detect the radiation dose, at least the following difficulties need to be solved: (1) accurately detecting the energy of a single radiation particle; (2) the radiation particles captured by the radiation particle detector are ensured to be completely collected in the radiation dose detection process, and omission is avoided.
The inventors of the present disclosure have also found that, typically, radiation particles enter the radiation particle detector in a single manner, and there are few instances where multiple radiation particles enter the radiation particle detector at the same time. Therefore, it can be considered that each electronic pulse signal output by the radiation particle detector includes information of each corresponding radiation particle, such as energy, lifetime, and the like. However, the electronic pulse signal output by the radiation particle detector is only less than 1 μ s wide, and the peak width is less than 0.1 μ s, so that it is necessary to design a proper acquisition technology to acquire each electronic pulse signal output by the radiation particle detector, so as to ensure the accuracy of radiation dose detection.
Fig. 1 shows a flow chart of a radiation dose detection method according to an embodiment of the present disclosure. As shown in fig. 1, the method includes the following steps S11 to S13.
In step S11, detecting the energy of the single radiation particle by using the electronic pulse signal output by the radiation particle detector;
in step S12, counting the number of the single radiation particles per unit time;
in step S13, a radiation dose per unit time is calculated based on the counted number per unit time and the energy of each corresponding radiation particle.
The present disclosure does not limit the manner in which the radiation dose is calculated using the number of individual radiation particles and their energies. For example, one calculation method may include weighting the energy of each detected radiation particle in a unit time, and then accumulating all the weighted energies to obtain the radiation dose in the unit time. For example, assuming that a total of 3 radiation particles are detected per unit time, the energy of each radiation particle is N1, N2 and N3, respectively, and the weight (i.e., the proportionality coefficient) of the energy of each particle is a1, a2 and a3, respectively, the radiation dose per unit time is a1 × N1+ a2 × N2+ a3 × N3. However, it will be understood by those skilled in the art that the above calculation method is only an example, and the present disclosure is not limited thereto.
By adopting the technical scheme, the energy of the single radiation particle is detected by using the electronic pulse signal output by the radiation particle detector and the number of the single radiation particle in unit time is counted, so that the capability information of the single radiation particle can be well kept, the radiation particles captured by the radiation particle detector are completely collected in the radiation dose detection process and cannot be missed, and the accuracy of the radiation dose detection can be ensured by accurately detecting the energy and the number of the single radiation particle. Moreover, because single radiation particles are detected independently, the influence of noise accumulation in the existing time integration method can be avoided, natural background radiation interference is avoided, and low power consumption in a background detection state is realized.
The detection of the energy of the individual radiation particles by the electronic pulse signal output by the radiation particle detector in step S11 can be implemented in various ways. Two exemplary implementations are given in this disclosure, one is a low power consumption detection mode and the other is a parallel acquisition detection mode. Also, the radiation dose detection method according to the embodiment of the present disclosure can detect the radiation dose using only the low power consumption detection mode; the radiation dose can also be detected only by using a parallel acquisition detection mode; of course, the low power consumption detection mode and the parallel acquisition detection mode can be switched based on preset switching conditions so as to meet the requirements of power consumption and precision.
The operation of the low power detection mode is described next. Firstly, the amplitude of the electronic pulse signal is detected, and then the amplitude of the electronic pulse signal is collected as the energy of the single radiation particle under the condition that the detected amplitude exceeds a preset pulse threshold value. The preset pulse threshold value may be set in consideration of the influence of factors such as background radiation interference of the natural environment. The detected amplitude exceeds a preset pulse threshold value, which indicates that the radiation particle detector captures radiation particles, and the amplitude of the electronic pulse signal is acquired under the condition; the detected amplitude is lower than the preset pulse threshold, which indicates that no radiation particles actually arrive at the moment, and it is possible that the radiation particle detector outputs the electronic pulse signal only because of the interference of the background radiation of the natural environment, so the amplitude of the electronic pulse signal is not collected in this case. Therefore, the low-power-consumption detection mode is suitable for scenes with small radiation particle quantity, power consumption can be reduced, radiation particles captured by the radiation particle detector can be completely collected in the radiation dose detection process, omission is avoided, and the radiation dose detection accuracy is further ensured.
In addition, in the low power consumption detection mode, the counting of the number of the single radiation particles in the unit time in step S12 may include: and counting the number of the amplitude values acquired in the unit time as the number of the single radiation particles in the unit time. In this way, the number of individual radiation particles per unit time can be easily and accurately obtained.
The workflow of the parallel acquisition detection mode is described next. Firstly, the electronic pulse signals are continuously acquired in parallel to obtain an electronic pulse envelope, and then the area of the electronic pulse envelope is calculated as the energy of the single radiation particle. For example, multiple circuits such as high-speed analog-to-digital converters can be used to acquire the electronic pulse signals in parallel at high speed, so that the acquisition capability of multiple speeds can be realized, and the precise envelope of the electronic pulse signals generated by single radiation particles can be acquired. Therefore, the parallel acquisition detection mode is suitable for the external scene with radioactive substances. Compared with a low-power-consumption detection mode, the power consumption of the parallel acquisition detection mode is higher, but the energy of a single radiation particle can be accurately calculated due to the fact that an accurate envelope can be obtained, and therefore the radiation dose can be detected more accurately.
In addition, in the parallel acquisition detection mode, the counting of the number of the single radiation particles in the unit time in the step S12 includes: and counting the number of the electronic pulse envelopes collected in the unit time as the number of the single radiation particles in the unit time. Because one electronic pulse signal corresponds to one radiation particle and one envelope can be obtained by parallelly and quickly acquiring one electronic pulse signal, the number of the envelopes acquired in unit time can be counted, and the number of the single radiation particles in unit time can be simply, conveniently and accurately obtained.
As can be seen from the above description, the low power consumption detection mode has lower power consumption and the parallel acquisition detection mode has higher precision, so if the low power consumption detection mode and the parallel acquisition detection mode are combined, both low power consumption and high precision of radiation dose detection can be achieved. Therefore, in one implementation, the radiation dose detection method according to the embodiment of the present disclosure further includes: comparing the calculated radiation dose with a preset radiation dose threshold; and switching between the low power consumption detection mode and the parallel acquisition detection mode based on the comparison result. The preset radiation dose threshold may be a preset radiation dose threshold based on safety experience, that is, a radiation dose threshold determined based on past experience, and may also be a natural environment background radiation dose. If the calculated radiation dose exceeds the preset radiation dose threshold, the outside radioactive substance is shown, and the parallel acquisition detection mode is more favorable, and if the calculated radiation dose is lower than the preset radiation dose threshold, the radiation particle number is less, and the low-power consumption detection mode is more favorable.
For example, assuming that a low power detection mode is currently employed, if the subsequently calculated radiation dose exceeds a preset radiation dose threshold, the low power detection mode is switched to the parallel acquisition detection mode to achieve accurate radiation dose detection, and if the subsequently calculated radiation dose continues to remain below the preset radiation dose threshold, the low power detection mode continues to be maintained to reduce power consumption. For another example, assuming that the parallel acquisition detection mode is currently adopted, if the radiation dose obtained by subsequent calculation is lower than the preset radiation dose threshold, preferably for several times, the parallel acquisition detection mode is switched to the low-power-consumption detection mode to reduce power consumption, wherein the switching is performed only when the radiation dose obtained by subsequent calculation is lower than the preset radiation dose threshold for several times, instead of switching once the radiation dose is lower, so that the external environment can be more accurately verified to actually enter a scene with a small number of radiation particles; and if the subsequently calculated radiation dose continues to exceed the preset radiation dose threshold, the parallel acquisition detection mode continues to be maintained to enable accurate detection of the radiation dose.
In addition, the radiation particle energy distribution differs for different radiation sources. Therefore, the radiation dose detection method according to the embodiment of the present disclosure further includes: sending a gain adjustment instruction to the radiation particle detector based on the distribution of the detected energy, wherein the gain adjustment instruction causes the radiation particle detector to adjust its output gain. Therefore, by controlling the detector output gain, radiation particle detection over a wide energy range can be achieved.
Fig. 2 shows a schematic block diagram of a radiation dose detection device according to an embodiment of the present disclosure. As shown in fig. 2, the apparatus includes: an energy detection module 21, configured to detect energy of a single radiation particle by using an electronic pulse signal output by the radiation particle detector; a microcontroller 22 for counting the number of the single radiation particles in a unit time, and calculating the radiation dose in the unit time based on the counted number in the unit time and the energy of each corresponding radiation particle detected by the energy detection module 21.
By adopting the technical scheme, the energy of the single radiation particle is detected by using the electronic pulse signal output by the radiation particle detector and the number of the single radiation particle in unit time is counted, so that the capability information of the single radiation particle can be well kept, the radiation particles captured by the radiation particle detector are completely collected in the radiation dose detection process and cannot be missed, and the accuracy of the radiation dose detection can be ensured by accurately detecting the energy and the number of the single radiation particle. Moreover, because single radiation particles are detected independently, the influence of noise accumulation in the existing time integration method can be avoided, natural background radiation interference is avoided, and low power consumption in a background detection state is realized.
Fig. 3 shows a further schematic block diagram of a radiation dose detection device according to an embodiment of the present disclosure. As shown in FIG. 3, the energy detection module 21 may include at least one of a low power energy detection sub-module 211 and a parallel acquisition energy detection sub-module 212, both of which are illustratively shown in FIG. 2.
With further reference to fig. 3, the low power energy detection submodule 211 includes a threshold detection circuit 2111 and a sample and hold circuit 2112. The threshold detection circuit 2111 is configured to detect an amplitude of the electronic pulse signal, compare the detected amplitude with a preset pulse threshold, and send a comparison result to the microcontroller 22. The sample-and-hold circuit 2112 is configured to collect and hold the amplitude of the electronic pulse signal. The microcontroller 22 is further configured to process the amplitude value collected by the sample-and-hold circuit 2112 to obtain the energy of a single radiation particle, if the comparison result indicates that the detected amplitude value exceeds the preset pulse threshold value. For example, if the amplitude output by the sample and hold circuit 2112 is an analog amplitude, the microcontroller 22 will first perform an analog-to-digital conversion on the analog amplitude output by the sample and hold circuit 2112, and then calculate the digital amplitude after the analog-to-digital conversion to obtain the energy of the single radiation particle. For another example, if the amplitude output by the sample and hold circuit 2112 is a digital amplitude, the microcontroller 22 directly processes the digital amplitude output by the sample and hold circuit 2112 to obtain the energy of the individual radiation particles. Additionally, in the event that the comparison indicates that the detected amplitude is below the preset pulse threshold, the microcontroller 22 may ignore the output of the sample and hold circuit 2112.
The preset pulse threshold setting may take into account the effects of factors such as natural environment background radiation interference. The amplitude detected by the threshold detection circuit 2111 exceeds the preset pulse threshold, indicating that a radiation particle is captured by the radiation particle detector, in which case the microcontroller 22 will process the amplitude output by the sample and hold circuit 2112 to derive the energy of the individual radiation particle. The amplitude detected by the threshold detection circuit 2111 is lower than the preset pulse threshold, indicating that no radiation particles are actually coming, which may cause the radiation particle detector to output an electronic pulse signal only due to the interference of the background radiation of the natural environment, so in this case, the microcontroller 22 ignores the output of the sample-and-hold circuit 2112. Therefore, the low-power-consumption energy detection submodule 211 is suitable for a scene with a small number of radiation particles, can reduce power consumption, and can ensure that the radiation particles captured by the radiation particle detector are all collected in the radiation dose detection process, so that omission is avoided, and the accuracy of radiation dose detection is further ensured.
In addition, in the case where the low-power-consumption energy detection submodule 211 is active, that is, during the detection of the energy of a single radiation particle by the low-power-consumption energy detection submodule 211, the microcontroller 22 counts the number of amplitude values acquired by the sample-and-hold circuit 2112 per unit time as the number of the single radiation particles per unit time. In this way, the number of individual radiation particles per unit time can be easily and accurately obtained.
In addition, the low-power-consumption energy detection sub-module 211 may further include a reset circuit (not shown in fig. 3) for resetting the outputs of the threshold detection circuit 2111 and the sample-and-hold circuit 2112 after the microcontroller 22 receives the amplitude value collected by the sample-and-hold circuit 2112. The reset circuit may also be used to reset the input of the sample and hold circuit 2112 after the microcontroller 22 receives the amplitude value collected by the sample and hold circuit 2112. That is, the reset circuit will perform the corresponding reset operation only if the comparison result of the threshold detection circuit 2111 indicates that the detected amplitude exceeds the preset pulse threshold and the microcontroller 22 has received the amplitude collected by the sample-and-hold circuit 2112. By performing the reset operation, erroneous data can be prevented from being erroneously transferred to the microcontroller 22.
Fig. 4 shows a circuit schematic of the low power energy detection submodule 211. In fig. 4, TP7 is the electronic pulse signal output by the radiation particle detector; TP6 is the comparison result of the threshold detection circuit 2111; TP3 is the reset signal from microcontroller 22; TP8 is an enable signal from microcontroller 22 for enabling amplifiers U3A and U3B; TP10 is the output signal of the sample-and-hold circuit 2112. In addition, the amplifier U3A realizes the comparison of the electronic pulse signal output by the radiation particle detector with the preset pulse threshold value through open-loop amplification. R23, R24 and D5 form a preset pulse threshold setting circuit to realize threshold filtering. Q1 is used to reset the threshold detection circuit 2111. The amplifier U3A may also be replaced with a comparator. The amplifier U3B, the R17 and the R18 form a closed loop amplifying circuit, and sampling and holding of the electronic pulse signal are achieved. Q2 is used to reset the sample-and-hold circuit 2112. Q3 and R21 are used to reset the input of amplifier U3B.
Reference is made back to fig. 3. The parallel acquisition energy detection submodule 212 includes a parallel acquisition channel 2121, the parallel acquisition channel 2121 is configured to continuously acquire the electronic pulse signal in parallel and send acquired data to the microcontroller 22, and the microcontroller 22 is further configured to obtain an electronic pulse envelope based on the acquired data acquired by the parallel acquisition channel 2121 and calculate an area of the electronic pulse envelope as the energy of the single radiation particle. For example, the parallel acquisition channels 2121 may be implemented using a plurality of circuits such as high-speed analog-to-digital converters, which enable a multi-speed acquisition capability to acquire an accurate envelope of the electrical pulse signal generated by a single radiation particle. Therefore, the parallel-acquisition energy detection sub-module 212 is suitable for a scene in which radioactive substances appear outside. Compared with the low-power-consumption energy detection submodule 211, the power consumption of the parallel acquisition energy detection submodule 212 is higher, but the energy of a single radiation particle can be accurately calculated due to the fact that an accurate envelope can be obtained, and further more accurate detection of radiation dose can be achieved. In addition, in this case, the microcontroller 22 may operate in a Direct Memory Access (DMA) mode.
In addition, in the case where the parallel-acquisition energy detection submodule 212 is active, that is, during the detection of the energy of a single radiation particle by the parallel-acquisition energy detection submodule 212, the microcontroller 22 counts the number of the electronic pulse envelopes obtained in the unit time as the number of the single radiation particle in the unit time. Because one electronic pulse signal corresponds to one radiation particle and one envelope can be obtained by parallelly and quickly acquiring one electronic pulse signal, the number of the envelopes acquired in unit time can be counted, and the number of the single radiation particles in unit time can be simply, conveniently and accurately obtained.
Since the low-power-consumption energy detection sub-module 211 and the parallel-acquisition energy detection sub-module 212 have advantages, they can be used in combination, so that both low power consumption and high radiation dose detection accuracy can be achieved. In this case, the microcontroller 22 is also configured to compare the calculated radiation dose with a preset radiation dose threshold; and based on the comparison result, switching between the low-power energy detection submodule 211 and the parallel-acquisition energy detection submodule 212. The preset radiation dose threshold may be a preset radiation dose threshold based on safety experience, that is, a radiation dose threshold determined based on past experience, and may also be a natural environment background radiation dose. If the calculated radiation dose exceeds the preset radiation dose threshold, it is more favorable to adopt the parallel acquisition energy detection sub-module 212, and if the calculated radiation dose is lower than the preset radiation dose threshold, it is more favorable to adopt the low-power-consumption energy detection sub-module 211.
In one embodiment, the microcontroller 22 may be further configured to send a gain adjustment instruction to the radiation particle detector based on the detected energy distribution, wherein the gain adjustment instruction causes the radiation particle detector to adjust its output gain. Thus, the problem of different energy distributions of the radiation particles of different radiation sources can be solved.
The working principle of the radiation dose detection device is described below by taking an example in which the radiation dose detection device includes a low-power-consumption energy detection sub-module 211 and a parallel-acquisition energy detection sub-module 212, and switching between the two.
First, the radiation dose detection device is started, the microcontroller 22 completes initialization, sets the output gain of the radiation particle detector to a preset value, and turns on and resets the threshold detection circuit 2111. Then, the threshold detection circuit 2111 detects whether the amplitude of the electronic pulse signal output from the radiation particle detector exceeds a preset pulse threshold, and the sample-and-hold circuit 2112 automatically acquires the amplitude of the electronic pulse signal. Then, under the condition that the threshold detection circuit 2111 detects that the amplitude of the electronic pulse signal exceeds the preset pulse threshold, the microcontroller 22 processes the amplitude of the electronic pulse signal acquired by the sample-and-hold circuit 2112 to obtain the energy of a single radiation particle; in the event that the threshold detection circuit 2111 detects that the amplitude of the electronic pulse signal is below the preset pulse threshold, the microcontroller 22 will ignore the output of the sample and hold circuit 2112. Then, after the microcontroller 22 has completed processing (e.g., analog-to-digital conversion) of the amplitude output by the sample-and-hold circuit 2112, the threshold detection circuit 2111 and the sample-and-hold circuit 2112 are reset in preparation for the next acquisition. At the same time, microcontroller 22 enters a sleep state. The microcontroller 22 then wakes up periodically and calculates the current real-time radiation dose using the number of single radiation particles collected per unit time and their energy. If the calculated radiation dose exceeds the preset radiation dose threshold, the microcontroller 22 sends alarm information, closes the low-power-consumption energy detection submodule 211 and opens the parallel acquisition energy detection submodule 212, that is, the switching between the low-power-consumption energy detection submodule 211 and the parallel acquisition energy detection submodule 212 is realized, so as to realize the accurate detection of the radiation dose.
Then, the parallel acquisition channel 2121 continuously acquires the electronic pulse signal output by the radiation particle detector in parallel at a high speed to obtain an electronic pulse envelope, and the area of the electronic pulse envelope is calculated by fitting as the energy of a single radiation particle. Then, the microcontroller 22 counts the number of the single radiation particles by using the number of the envelopes obtained in the unit time, and calculates the radiation dose of the current environment by using the number of the single radiation particles collected in the unit time and the corresponding energy. If the measured particle energy distribution is not within the optimal operating range of the parallel high-speed acquisition channel, the microcontroller 22 adjusts the output gain of the radiation particle detector based on the particle energy distribution, thereby continuously correcting the test value to obtain an accurate radiation dose. Moreover, the microcontroller 22 compares the calculated radiation dose with a preset radiation dose threshold, and if the calculated radiation dose is continuously lower than the preset radiation dose threshold (for example, continuously lower than the preset radiation dose threshold for several times), the microcontroller 22 controls the parallel acquisition channel 2121 to be closed and the low-power-consumption energy detection submodule 211 to be opened, so that the parallel acquisition energy detection submodule 212 and the low-power-consumption energy detection submodule 211 are switched to reduce power consumption.
The preferred embodiments of the present disclosure are described in detail with reference to the accompanying drawings, however, the present disclosure is not limited to the specific details of the above embodiments, and various simple modifications may be made to the technical solution of the present disclosure within the technical idea of the present disclosure, and these simple modifications all belong to the protection scope of the present disclosure.
It should be noted that the various features described in the above embodiments may be combined in any suitable manner without departing from the scope of the invention. In order to avoid unnecessary repetition, various possible combinations will not be separately described in this disclosure.
In addition, any combination of various embodiments of the present disclosure may be made, and the same should be considered as the disclosure of the present disclosure, as long as it does not depart from the spirit of the present disclosure.
Claims (10)
1. A radiation dose detection method, comprising:
detecting the energy of a single radiation particle by using an electronic pulse signal output by the radiation particle detector;
counting the number of the single radiation particles in unit time;
calculating a radiation dose per unit time based on the counted number per unit time and the energy of each corresponding radiation particle;
the energy of a single radiation particle is detected by using an electronic pulse signal output by the radiation particle detector, and the detection is realized by one of a low-power consumption detection mode and a parallel acquisition detection mode:
(1) in the low power detection mode: detecting the amplitude of the electronic pulse signal; collecting the amplitude of the electronic pulse signal as the energy of the single radiation particle under the condition that the detected amplitude exceeds a preset pulse threshold;
(2) in the parallel acquisition detection mode: continuously acquiring the electronic pulse signals in parallel to obtain an electronic pulse envelope, and calculating the area of the electronic pulse envelope as the energy of the single radiation particle;
the method further comprises the following steps: comparing the calculated radiation dose with a preset radiation dose threshold; and switching between the low power consumption detection mode and the parallel acquisition detection mode based on a comparison result, wherein the preset radiation dose threshold is a preset radiation dose threshold based on safety experience or a natural environment background radiation dose.
2. The method of claim 1, wherein in the low power detection mode, counting the number of the single radiation particles per unit time comprises:
and counting the number of the amplitude values acquired in the unit time as the number of the single radiation particles in the unit time.
3. The method of claim 1, wherein in the parallel acquisition detection mode, the counting the number of the single radiation particles per unit time comprises:
and counting the number of the electronic pulse envelopes collected in the unit time as the number of the single radiation particles in the unit time.
4. The method of claim 1, further comprising:
sending a gain adjustment instruction to the radiation particle detector based on the distribution of the detected energy, wherein the gain adjustment instruction causes the radiation particle detector to adjust its output gain.
5. A radiation dose detecting apparatus, characterized in that the apparatus comprises:
the energy detection module is used for detecting the energy of a single radiation particle by using the electronic pulse signal output by the radiation particle detector;
a microcontroller for counting the number of the single radiation particles in a unit time and calculating a radiation dose in the unit time based on the counted number in the unit time and the energy of each corresponding radiation particle detected by the energy detection module;
wherein, the energy detection module includes low-power consumption energy detection submodule and parallel acquisition energy detection submodule, wherein:
the low-power-consumption energy detection submodule comprises a threshold detection circuit and a sample-and-hold circuit, wherein: the threshold detection circuit is used for detecting the amplitude of the electronic pulse signal, comparing the detected amplitude with a preset pulse threshold and sending a comparison result to the microcontroller, the sample-and-hold circuit is used for collecting and holding the amplitude of the electronic pulse signal, and the microcontroller is also used for processing the amplitude collected by the sample-and-hold circuit to obtain the energy of the single radiation particle when the comparison result shows that the detected amplitude exceeds the preset pulse threshold;
the parallel acquisition energy detection submodule comprises a parallel acquisition channel, the parallel acquisition channel is used for continuously acquiring the electronic pulse signal in parallel and sending acquired data to the microcontroller, the microcontroller is also used for obtaining an electronic pulse envelope based on the acquired data acquired by the parallel acquisition channel and calculating the area of the electronic pulse envelope as the energy of the single radiation particle;
the microcontroller is further configured to: comparing the calculated radiation dose with a preset radiation dose threshold; and switching between the low-power-consumption energy detection submodule and the parallel acquisition energy detection submodule based on a comparison result, wherein the preset radiation dose threshold is a preset radiation dose threshold based on safety experience or a natural environment background radiation dose.
6. The apparatus of claim 5, wherein the microcontroller counts the number of amplitude values collected by the sample and hold circuit per unit time as the number of single radiation particles per unit time, with the low power energy detection submodule functioning.
7. The apparatus of claim 5, wherein the microcontroller counts the number of the resulting electronic pulse envelopes per unit time as the number of the single radiation particles per unit time with the parallel acquisition energy detection submodule functioning.
8. The apparatus of claim 5, wherein the microcontroller is further configured to:
sending a gain adjustment instruction to the radiation particle detector based on the distribution of the detected energy, wherein the gain adjustment instruction causes the radiation particle detector to adjust its output gain.
9. The apparatus of any of claims 5-8, wherein the low power energy detection submodule further comprises a reset circuit configured to reset the outputs of the threshold detection circuit and the sample-and-hold circuit after the microcontroller receives the amplitude value collected by the sample-and-hold circuit.
10. The apparatus of claim 9, wherein the reset circuit is further configured to reset the input of the sample and hold circuit after the microcontroller receives the amplitude value collected by the sample and hold circuit.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910663174.9A CN110456402B (en) | 2019-07-22 | 2019-07-22 | Radiation dose detection method and device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910663174.9A CN110456402B (en) | 2019-07-22 | 2019-07-22 | Radiation dose detection method and device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110456402A CN110456402A (en) | 2019-11-15 |
| CN110456402B true CN110456402B (en) | 2021-09-10 |
Family
ID=68482969
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910663174.9A Active CN110456402B (en) | 2019-07-22 | 2019-07-22 | Radiation dose detection method and device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110456402B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111103684B (en) * | 2020-01-06 | 2020-11-06 | 深圳市大德激光技术有限公司 | Multi-head cooperative control method and system for beam energy of laser light splitting |
Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4767929A (en) * | 1986-10-06 | 1988-08-30 | The United States Of America As Represented By The United State Department Of Energy | Extended range radiation dose-rate monitor |
| JPH06180367A (en) * | 1992-12-11 | 1994-06-28 | Shimadzu Corp | Radiation measuring equipment |
| JPH07306267A (en) * | 1994-05-11 | 1995-11-21 | Aloka Co Ltd | Radiation measuring equipment |
| CN1511266A (en) * | 2001-05-28 | 2004-07-07 | 浜松光子学株式会社 | Energy measuring method and device |
| CN105866557A (en) * | 2016-03-22 | 2016-08-17 | 成都理工大学 | Time and energy double-spectrum synchronization measurement system for achieving GHZ pulse passing rate |
| CN108196293A (en) * | 2018-03-14 | 2018-06-22 | 中广核贝谷科技股份有限公司 | One kind is based on scintillator detector dosage rate detection method |
| CN108345022A (en) * | 2017-01-22 | 2018-07-31 | 中国科学院国家空间科学中心 | A kind of measuring device and method of space charged particle dose of radiation |
| CN108964637A (en) * | 2018-05-18 | 2018-12-07 | 成都理工大学 | A kind of superelevation percent of pass current mode digitized pulse processing method based on FPGA |
| CN109932742A (en) * | 2019-03-15 | 2019-06-25 | 苏州笃瑞监测科技有限公司 | A kind of portable radiant health-monitoring installation based on Spectrum acquisition |
-
2019
- 2019-07-22 CN CN201910663174.9A patent/CN110456402B/en active Active
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4767929A (en) * | 1986-10-06 | 1988-08-30 | The United States Of America As Represented By The United State Department Of Energy | Extended range radiation dose-rate monitor |
| JPH06180367A (en) * | 1992-12-11 | 1994-06-28 | Shimadzu Corp | Radiation measuring equipment |
| JPH07306267A (en) * | 1994-05-11 | 1995-11-21 | Aloka Co Ltd | Radiation measuring equipment |
| CN1511266A (en) * | 2001-05-28 | 2004-07-07 | 浜松光子学株式会社 | Energy measuring method and device |
| CN105866557A (en) * | 2016-03-22 | 2016-08-17 | 成都理工大学 | Time and energy double-spectrum synchronization measurement system for achieving GHZ pulse passing rate |
| CN108345022A (en) * | 2017-01-22 | 2018-07-31 | 中国科学院国家空间科学中心 | A kind of measuring device and method of space charged particle dose of radiation |
| CN108196293A (en) * | 2018-03-14 | 2018-06-22 | 中广核贝谷科技股份有限公司 | One kind is based on scintillator detector dosage rate detection method |
| CN108964637A (en) * | 2018-05-18 | 2018-12-07 | 成都理工大学 | A kind of superelevation percent of pass current mode digitized pulse processing method based on FPGA |
| CN109932742A (en) * | 2019-03-15 | 2019-06-25 | 苏州笃瑞监测科技有限公司 | A kind of portable radiant health-monitoring installation based on Spectrum acquisition |
Also Published As
| Publication number | Publication date |
|---|---|
| CN110456402A (en) | 2019-11-15 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| EP2176684B1 (en) | Apparatus and method for generating countable pulses from impinging x-ray photons, and corresponding imaging device | |
| US8415635B2 (en) | Particle-counting apparatus with pulse shortening | |
| US10180351B2 (en) | Dark current compensation for photon counting circuit | |
| EP1966996B1 (en) | Event detection for digital radiography detector | |
| EP2395566B1 (en) | Signal processing device and photodetection device | |
| EP2734861B1 (en) | Photon counting imaging method and device with instant retrigger capability | |
| US20110036989A1 (en) | Counting detector | |
| US20080018505A1 (en) | Adaptive data acquisition for an imaging system | |
| US20080135731A1 (en) | Photoarray for Detecting Time-Dependent Image Data | |
| US20160299002A1 (en) | Detection device for detecting photons and method therefore | |
| US10234574B2 (en) | Radiation imaging apparatus, radiation imaging system, and irradiation start detection method | |
| CN108293096B (en) | Radiation detector and x-ray imaging system | |
| CN110476086B (en) | pulse shaper | |
| US8866094B2 (en) | Radiation detector | |
| CN110456402B (en) | Radiation dose detection method and device | |
| US20160377741A1 (en) | Signal processor and radiation detection device | |
| CN110362529B (en) | Energy particle detector signal processing system and method | |
| EP2728380A1 (en) | Driver circuit and readout circuit | |
| US20080135771A1 (en) | Signal Discriminator for Radiation Detection System and Method | |
| JP2017044518A (en) | Signal processing device and radiation measurement device | |
| Frizzi et al. | The SIDDHARTA chip: A CMOS multi-channel circuit for silicon drift detectors readout in exotic atoms research | |
| US20240036219A1 (en) | Electric circuitry for baseline extraction in a photon counting system | |
| CN117157556A (en) | Baseline restorer circuit | |
| US20220323031A1 (en) | Method and system for high bit depth imaging | |
| CN115327599A (en) | Nuclear pulse energy measuring device and compensation method based on pulse average width |
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 |