CN113466923A

CN113466923A - Method and apparatus for detecting radioactive substance

Info

Publication number: CN113466923A
Application number: CN202010247846.0A
Authority: CN
Inventors: 图雅高娃; 赵崑; 徐晓娜; 靳增雪
Original assignee: Nuctech Co Ltd
Current assignee: Nuctech Co Ltd
Priority date: 2020-03-31
Filing date: 2020-03-31
Publication date: 2021-10-01
Anticipated expiration: 2040-03-31
Also published as: CN113466923B

Abstract

The present disclosure provides a radioactive substance detection method, the method including: detecting an object with a radioactive substance with a plurality of detectors to obtain a plurality of energy spectra for the radioactive substance; screening the plurality of energy spectrums to screen effective energy spectrums from the plurality of energy spectrums; combining the effective energy spectrums to obtain a synthesized energy spectrum; and determining the category of the radioactive substance based on the composite energy spectrum. The present disclosure also provides a radioactive substance detection apparatus, an electronic device, and a non-transitory computer-readable medium.

Description

Method and apparatus for detecting radioactive substance

Technical Field

The present disclosure relates to the field of radioactive substance detection, and more particularly, to a radioactive substance detection method, a radioactive substance detection apparatus, an electronic device, and a computer-readable storage medium.

Background

The portal type radioactive substance detection system is a device for preventing radioactive substances from smuggling and being carried illegally, and plays an increasingly important role in the fields of customs, quality inspection and the like. Portal radioactive material detection systems are often equipped with multiple detectors. However, the main purpose of configuring multiple detectors at the present stage is to detect different positions of the vehicle, so as to reduce false positives caused by the fact that the radiation is far away from the detectors. Alternatively, the position of the radioactive material in the vehicle can be roughly estimated based on the difference in the counting rates of the different detectors.

Currently, there is no clear and effective way to integrate the use of individual detector spectra to improve the accuracy of the identification of radioactive materials. The existing method for integrating the energy spectrums of multiple detectors is mainly a method for integrating the peak searching result of each energy spectrum or integrating the final radioactive substance identification result and the like at the later end of the data processing process. The methods have limited improvement degree on the identification accuracy of the radioactive substances, and even the situation that the single detector can correctly identify the radioactive substances and the result after the integration of multiple detectors is false alarm or false alarm can occur.

Disclosure of Invention

In order to solve the above problem, a first aspect of the present application provides a radioactive substance detection method, which may include: detecting an object with a radioactive substance with a plurality of detectors to obtain a plurality of energy spectra for the radioactive substance; screening the plurality of energy spectrums to screen effective energy spectrums from the plurality of energy spectrums; combining the effective energy spectrums to obtain a synthesized energy spectrum; and determining a class of the radioactive material based on the composite energy spectrum.

According to a first aspect, screening the plurality of energy spectra to screen an effective energy spectrum from the plurality of energy spectra may comprise: selecting a detector from the plurality of detectors that is closest to the radioactive material based on the plurality of energy spectra produced by the plurality of detectors; selecting an energy spectrum with the highest possibility that the irradiation on the radioactive substance is front irradiation from energy spectrums of detectors closest to the radioactive substance; and determining an energy spectrum in which the irradiation of the radioactive substance is most likely to be front irradiation as the effective energy spectrum.

According to a first aspect, selecting the detector closest to the radioactive material from the plurality of detectors may include: calculating a gamma particle count rate for each detector of the plurality of detectors; and determining the detector with the maximum gamma particle count rate as the detector closest to the radioactive material.

According to the first aspect, selecting the energy spectrum with the highest probability that the irradiation of the radioactive substance is front irradiation from the energy spectra of the detector closest to the radioactive substance may include: determining a trend of gamma particle count rates for each of the energy spectra of the detector nearest to the radioactive material; and determining an energy spectrum in which the trend of the gamma particle counting rate satisfies a predetermined rule as an energy spectrum having the highest possibility of irradiation of the radioactive substance as front irradiation.

According to the first aspect, the effective energy spectrum is further normalized before being combined.

According to a first aspect, normalizing the effective energy spectrum may comprise: for each of the effective energy spectra, dividing the gamma particle count for each pass in the energy spectrum by the energy for that pass to obtain a unit energy count density spectrum; adding the energy count density spectra for the effective energy spectra to obtain a synthesized energy count density spectrum; and for the synthesized energy count density spectrum, multiplying, for each track, the energy count for the track by the corresponding energy count for the track to obtain the synthesized energy spectrum.

A second aspect of the present application provides a radioactive substance detection apparatus, which may include: a plurality of detectors configured to detect objects with radioactive material to obtain a plurality of energy spectra for the radioactive material; a screening module configured to screen the plurality of energy spectra to screen an effective energy spectrum from the plurality of energy spectra; a merging module configured to merge the effective energy spectra to obtain a composite energy spectrum; and a determination module configured to determine a category of the radioactive material based on the composite energy spectrum.

A third aspect of the present application provides an electronic device, which may include: one or more processors; and memory for storing one or more programs, wherein the one or more programs, when executed by the one or more processors, cause the one or more processors to implement the method according to the first aspect.

A fourth aspect of the present application provides a computer readable storage medium having stored thereon executable instructions which, when executed by a processor, cause the processor to carry out the method according to the first aspect.

The present disclosure relates to a radioactive substance detection system that uses a plurality of orientation detectors to synthesize a plurality of energy spectra measured simultaneously to enhance effective information and reduce the influence of statistical fluctuations and interfering nuclides in the environment, thereby improving the accuracy of radioactive substance identification.

According to the physical characteristics that when a vehicle passes through a detection channel, detectors in different directions away from radioactive substances form different distribution characteristics and strong and weak energy spectrums, the method for screening the energy spectrums and key information in the energy spectrums is provided. And the energy spectrum is converted into the density spectrum, so that the resampling technology can be applied to the trace value spectrum data, and the problem of normalization during energy spectrum combination is solved.

Drawings

The above and other embodiments and features of the present disclosure will become more apparent by describing in detail embodiments thereof with reference to the attached drawings in which:

fig. 1 schematically illustrates a system architecture of a radioactive material detection method according to an embodiment of the present disclosure;

FIG. 2 schematically illustrates a diagram of an exemplary arrangement of a probe according to an embodiment of the present disclosure;

FIG. 3 schematically illustrates a graph of an interference energy spectrum and an effective energy spectrum of a detector according to an embodiment of the disclosure;

FIG. 4 schematically illustrates a flow chart of a radioactive material detection method according to an embodiment of the present disclosure;

FIG. 5 schematically illustrates a flow chart of an example method of screening a plurality of energy spectra to screen an effective energy spectrum from the plurality of energy spectra, in accordance with an embodiment of the present disclosure;

FIG. 6 schematically illustrates a flow chart of an example method of selecting a detector closest to a radioactive material from a plurality of detectors according to an embodiment of the disclosure;

fig. 7 schematically illustrates a flowchart of an example method of selecting an energy spectrum with the highest probability of front-side illumination for irradiation of a radioactive substance from energy spectra of detectors closest to the radioactive substance according to an embodiment of the present disclosure;

FIG. 8 schematically illustrates a flow chart of an example method of normalizing an effective energy spectrum according to an embodiment of the disclosure;

FIG. 9 schematically shows a graph before and after normalization of an effective energy spectrum and a graph after synthesis according to an embodiment of the disclosure;

fig. 10 schematically illustrates a block diagram of a radioactive material detection apparatus according to an embodiment of the present disclosure; and

fig. 11 schematically illustrates a block diagram of an electronic device suitable for implementing the radioactive material detection method according to an embodiment of the present disclosure.

Detailed Description

Specific embodiments of the present invention will be described in detail below, and it should be noted that the embodiments described herein are only for illustration and are not intended to limit the present invention. In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. However, it will be apparent to one of ordinary skill in the art that: it is not necessary to employ these specific details to practice the present invention. In other instances, well-known circuits, materials, or methods have not been described in detail in order to avoid obscuring the present invention.

Throughout the specification, reference to "one embodiment," "an embodiment," "one example," or "an example" means: the particular features, structures, or characteristics described in connection with the embodiment or example are included in at least one embodiment of the invention. Thus, the appearances of the phrases "in one embodiment," "in an embodiment," "one example" or "an example" in various places throughout this specification are not necessarily all referring to the same embodiment or example. Furthermore, the particular features, structures, or characteristics may be combined in any suitable combination and/or sub-combination in one or more embodiments or examples.

It will be understood that when an element is referred to as being "coupled" or "connected" to another element, it can be directly coupled or connected to the other element or intervening elements may be present. In contrast, when an element is referred to as being "directly coupled" or "directly connected" to another element, there are no intervening elements present.

Further, as used herein, the term "and/or" includes any and all combinations of one or more of the associated listed items.

It will be understood that a noun in the singular corresponding to a term may include one or more things unless the relevant context clearly dictates otherwise. As used herein, each of the phrases such as "a or B," "at least one of a and B," "at least one of a or B," "A, B or C," "at least one of A, B and C," and "at least one of A, B or C" may include all possible combinations of the items listed together with the respective one of the plurality of phrases. As used herein, terms such as "1 st" and "2 nd" or "first" and "second" may be used to distinguish one element from another element simply and not to limit the elements in other respects (e.g., importance or order).

As used herein, the term "module" may include units implemented in hardware, software, or firmware, and may be used interchangeably with other terms (e.g., "logic," "logic block," "portion," or "circuitry"). A module may be a single integrated component adapted to perform one or more functions or a minimal unit or portion of the single integrated component. For example, according to an embodiment, the modules may be implemented in the form of Application Specific Integrated Circuits (ASICs).

It should be understood that the various embodiments of the present disclosure and the terms used therein are not intended to limit the technical features set forth herein to specific embodiments, but include various changes, equivalents, or alternatives to the respective embodiments. Unless otherwise explicitly defined herein, all terms are to be given their broadest possible interpretation, including meanings implied in the specification and meanings understood by those skilled in the art and/or defined in dictionaries, papers, etc.

Further, those of ordinary skill in the art will appreciate that the drawings provided herein are for illustrative purposes and are not necessarily drawn to scale. For the description of the figures, like reference numerals may be used to refer to like or related elements. The present disclosure will be described below by way of example with reference to the accompanying drawings.

It should be noted that, in the prior art, when the energy spectrum statistics of a single detector is not ideal, the effect of the radioactive substance identification algorithm is not ideal, and false alarm and false negative alarm are likely to occur. At the moment, the energy spectrums of the plurality of detectors are combined into one energy spectrum to be identified, so that the statistics of the energy spectrums can be effectively improved, and the identification accuracy is obviously improved.

Based on this, embodiments of the present disclosure provide a radioactive substance detection method for improving the identification accuracy of a radioactive substance and an apparatus to which the method can be applied. The method comprises the following steps: detecting an object with a radioactive substance with a plurality of detectors to obtain a plurality of energy spectra for the radioactive substance; screening the plurality of energy spectrums to screen effective energy spectrums from the plurality of energy spectrums; combining the effective energy spectrums to obtain a synthesized energy spectrum; and determining the category of the radioactive substance based on the composite energy spectrum.

The present disclosure will be described in detail below with reference to specific embodiments with reference to the attached drawings.

Fig. 1 schematically shows a system architecture of a radioactive substance detection method according to an embodiment of the present disclosure. The system architecture 100 may include a central processing unit 101, a network 102, and a detection channel 103.

In the detection passage 103, a vehicle 104 carrying radioactive substances a and B passes therethrough (for example, in the direction of the broken-line arrow).

In the exemplary embodiment, vehicle 104 is only an example of an object that includes radioactive material therein, and is not limiting.

In an exemplary embodiment, the radioactive materials a and B may be the same or different.

On both sides of the detection channel 103, detectors 105 are arranged.

An example arrangement of the detector 105 in the detection channel is shown in fig. 2.

In the exemplary embodiment, when a vehicle 104 carrying radioactive substances a and B passes through the detection passage 103, the detectors 105 located on both sides of the detection passage 103 detect the vehicle 104, thereby obtaining a plurality of energy spectra.

In an exemplary embodiment, the detector 105 may periodically detect the vehicle 104.

In an exemplary embodiment, the detector may continuously detect the vehicle 104.

The detector 105 may be configured to send the generated energy spectrum to the central processing unit 101 via the network 102 for processing by the central processing unit 101.

The central processing unit 101 may be configured to receive the energy spectrum from the detector 105 via the network 104, screen and synthesize the received energy spectrum to obtain a composite energy spectrum, and determine the categories of radioactive materials a and B carried on the vehicle 104 based on the composite energy spectrum.

The detailed operation of the central processing unit 101 for determining the category of the radioactive material based on the plurality of energy spectra obtained by the plurality of detectors will be discussed in detail below.

The central processing unit 101 may include a processor (not shown), a memory (not shown), a communication module (not shown), and the like.

The processor of the central processing unit 101 may be configured to: the spectra are screened and synthesized to obtain a composite spectrum, and the categories of radioactive materials a and B carried on the vehicle 104 are determined based on the composite spectrum.

The memory of the central processing unit 101 may store instructions, data, and the like relating to the method for performing radioactive substance detection. It will be understood by those skilled in the art that the memory of the central processing unit 101 may optionally store various suitable information, which will not be described in detail herein.

The communication module in the central processing unit 101 may support establishing a direct (e.g., wired) communication channel or a wireless communication channel between the central processing unit 101 and an external electronic device (e.g., the probe 105), and performing communication via the established communication channel. For example, the communication module receives the energy spectrum from the probe via the network 102.

The communication module may include one or more communication processors capable of operating independently of a processor (e.g., an Application Processor (AP)) and supporting wired and/or wireless communication. According to an embodiment of the present disclosure, the communication module may include a wireless communication module (e.g., a cellular communication module, a short-range wireless communication module, or a Global Navigation Satellite System (GNSS) communication module) or a wired communication module (e.g., a Local Area Network (LAN) communication module or a Power Line Communication (PLC) module). A respective one of the communication modules may communicate with an external electronic device via a first network (e.g., a short-range communication network such as bluetooth, wireless fidelity (Wi-Fi) direct, or infrared data association (IrDA)) or a second network (e.g., a long-range communication network such as a cellular network, the internet, or a computer network (e.g., a LAN or a Wide Area Network (WAN)). These various types of communication modules may be implemented as a single component (e.g., a single chip), or may be implemented as multiple components (e.g., multiple chips) that are separate from one another. The wireless communication module may identify and authenticate an electronic device in a communication network, such as a first network or a second network, using subscriber information (e.g., International Mobile Subscriber Identity (IMSI)) stored in the subscriber identity module.

In addition, the central processing unit 101 may further include a display, a microphone, and the like for displaying or broadcasting the kind, the degree of danger, whether forbidden, the amount, the size, and the like of the radioactive material currently being detected.

Fig. 2 schematically shows a diagram of an exemplary arrangement of a detector according to an embodiment of the present disclosure. The diagram shown in fig. 2 is also a cross-sectional view taken in a direction perpendicular to the direction of vehicle travel in fig. 1 (e.g., the direction indicated by the dashed arrow).

In fig. 2, 8 detectors 105-1 to 105-8 are symmetrically arranged on both sides of the detection channel 103.

However, this is merely an example, and in other exemplary embodiments, fewer or more detectors may be provided.

In other exemplary embodiments, the plurality of detectors may be asymmetrically disposed on both sides of the detection channel 103.

In other exemplary embodiments, the detectors may be arranged in any suitable manner as desired.

As can be seen from fig. 1, when the vehicle 104 carrying the radioactive materials a and B passes through the detection passage 103, the angles between the radioactive materials a and B and the respective detectors become smaller and smaller, and then become smaller and larger. In this case, the process of detecting the radioactive substance by the detector is as follows: probing with progressively smaller angles-probing with an angle of 0-probing with progressively larger angles. Wherein the angle is defined by a line between the detector and the radioactive material and a direction perpendicular to the direction of travel of the vehicle. When the angle is 0, the radioactive material is aligned with the front of the detector.

In an exemplary embodiment, the angled detection is referred to as side detection of radioactive material.

In the energy spectrum obtained under the condition of lateral detection, the total peak area of each energy branch of the radioactive substance deviates from the standard value of the branch ratio, the area of the formed compton plateau at the low energy end is also higher, and the change trend of the gamma particle counting rate is not obvious at the moment, so that the total energy peak cannot be clearly distinguished. The energy spectrum obtained in the case of a side detection therefore has an interfering effect on the identification of radioactive substances.

In an exemplary embodiment, detection at an angle of 0 is referred to as a frontal detection of radioactive material.

In the energy spectrum obtained under the condition of front detection, the ratio of the total energy peak area of each energy branch of the radioactive substance is close to the standard value of the branch ratio, the formed Compton plateau is relatively gentle, the change trend of the gamma particle counting rate is very obvious, and the total energy peak can be clearly distinguished. Therefore, the energy spectrum obtained under the condition of positive detection has a positive effect on the identification of radioactive substances, and is an effective energy spectrum.

Fig. 3 schematically illustrates a diagram of an interference energy spectrum and an effective energy spectrum of a detector according to an embodiment of the disclosure.

Fig. 3 shows the energy spectrum of the detector when it is front-side illuminated (fig. 3 (a)) with Co60 and side-illuminated (fig. 3 (b)) with Co 60.

As can be seen from fig. 3, in the energy spectrum obtained by front-side irradiation shown in (a) in fig. 3, two characteristic peaks of Co60 are very obvious, the peak shape is much higher than the baseline, the peak area ratio is approximately 1: 1, and the nuclide identification algorithm can easily make a correct judgment.

In the energy spectrum obtained by the side illumination in fig. 3 (b), the energy spectrum shape is relatively irregular, and although two characteristic peaks of Co60 exist, the peak shape is not so obvious, and is not much higher than the base line, and the effective area is not sufficient. And an interference peak is arranged behind the radionuclide identification algorithm, so that a correct judgment can be difficult.

At this time, if the energy spectrum in (a) in fig. 3 and the energy spectrum in (b) in fig. 3 are directly superimposed as in the prior art, the energy spectrum in (b) in fig. 3 has a negative influence on the recognition, and the recognition result after the superimposition is even worse than the recognition result by simply using the energy spectrum in (a) in fig. 3.

Based on this, before the energy spectrums are combined, the energy spectrums need to be screened, and effective energy spectrums having positive effects on final identification results are screened from a plurality of energy spectrums.

Fig. 4 schematically illustrates a flow chart of a radioactive material detection method according to an embodiment of the present disclosure.

As shown in fig. 4, the method includes the following operations.

In operation S401, an object (e.g., vehicle 104 in fig. 1 and 2) with radioactive materials (e.g., radioactive materials a and B in fig. 1 and 2) is detected with a plurality of detectors (e.g., detector 105 in fig. 1 and 2) located on both sides of the detection channel to obtain a plurality of energy spectra for the radioactive materials.

In operation S403, the central processing unit 101 screens the plurality of energy spectra obtained in operation S301 to screen an effective energy spectrum from the plurality of energy spectra.

As described above, the effective energy spectrum is an energy spectrum obtained when the detector detects the radioactive substance on the front side.

In operation S405, the central processing unit 101 combines the effective energy spectrums screened in operation S403 to obtain a composite energy spectrum.

In operation S407, the central processing unit 101 determines the category of the radioactive substance based on the composite energy spectrum obtained in operation S405.

Fig. 5 schematically illustrates a flow chart of an example method of screening a plurality of energy spectra to screen an effective energy spectrum from the plurality of energy spectra, according to an embodiment of the present disclosure.

As shown in fig. 5, the method includes the following operations.

In operation S501, the central processing unit 101 selects a detector closest to the radioactive substance from the plurality of detectors based on the plurality of energy spectra generated by the plurality of detectors.

As shown in fig. 2, the detectors closest to the radioactive material a should be the detectors 105-7 and 105-8. The detector closest to the radioactive material B should be the detector 105-1.

In operation S503, the central processing unit 101 selects an energy spectrum having the highest possibility of front irradiation of the radioactive substance from the energy spectra of the detectors closest to the radioactive substance.

In operation S505, the central processing unit 101 determines the energy spectrum having the highest possibility of irradiation of the radioactive substance as front irradiation as the effective energy spectrum.

FIG. 6 schematically illustrates a flow chart of an example method of selecting a detector closest to a radioactive material from a plurality of detectors according to an embodiment of the disclosure.

As shown in fig. 6, the method includes the following operations.

In operation S601, the central processing unit 101 calculates a gamma particle count rate for each of the plurality of detectors.

In an exemplary embodiment, the central processing unit 101 may obtain the gamma particle count rate by summing the gamma particle counts for each pass in the energy spectrum of each detector and then dividing the summed gamma particle counts by the detection time duration of that detector.

In an exemplary embodiment, when the detector periodically detects the radioactive substance, the time period between the detector beginning to detect the end of the detection is the detection duration of the detector.

For example, if the detector starts the first detection at t1, ends the first detection at t2, starts the second detection at t3, and ends the second detection at t4, the detection time of the detector is t1-t2, which is t3-t 4.

In the exemplary embodiment, the detection time periods of the detectors are different because the models, configurations, and the like of the detectors are different.

In an exemplary embodiment, the detection durations of the detectors 105-1 to 105-8 in FIG. 2 may be the same or different.

In operation S603, the central processing unit 101 determines the detector having the largest gamma particle count rate as the detector closest to the radioactive material.

Fig. 7 schematically shows a flowchart of an example method of operation S503 according to an embodiment of the present disclosure.

As shown in fig. 7, the method includes the following operations.

In operation S701, the central processing unit 101 determines a trend of the gamma particle count rate for each of the energy spectra of the detectors closest to the radioactive substance.

In operation S703, the central processing unit 101 determines an energy spectrum in which the trend of the gamma particle count rate satisfies a predetermined rule as an energy spectrum in which the irradiation of the radioactive substance is most likely to be front irradiation.

In an exemplary embodiment, the spectrum in which the change in the gamma particle count rate exhibits a significant upward-downward trend is a spectrum that has a positive effect on identification, and the more significant the upward-downward trend is, the greater the positive effect is.

In an exemplary embodiment, an energy spectrum in which the trend of the gamma particle count rate satisfies a predetermined level may be determined as an energy spectrum in which the irradiation of the radioactive substance is most likely to be front irradiation.

In the exemplary embodiment, it is assumed that the trend of the gamma particle count rate is classified into 4 levels, the trend of level 1 is least significant, and the trend of level 4 is most significant. At this time, the predetermined level is set to level 3.

In this case, the spectrum in which the trend of the gamma particle count rate is equal to or greater than level 3 is the spectrum in which the irradiation of the radioactive substance is most likely to be the front irradiation. The energy spectrum corresponding to level 3 is a side illumination with a very small angle, which can be considered approximately as a front illumination. The spectrum corresponding to level 4 is then full front illumination.

Due to individual differences of the detectors, the trace value-energy scales of the energy spectrum are different, and the energy represented by each trace on the abscissa of the energy spectrum is also different.

For this reason, the effective energy spectrum needs to be normalized, so that the final identification result is more accurate.

Fig. 8 schematically illustrates a flow chart of an example method of normalizing an effective energy spectrum according to an embodiment of the present disclosure.

Fig. 9 schematically shows graphs before and after normalization of the effective energy spectrum, and a graph after synthesis, according to an embodiment of the present disclosure.

The normalization operation will be described below in conjunction with fig. 8 and 9.

As shown in fig. 8, the method includes the following operations.

In operation S801, the central processing unit 101 divides, for each of the effective energy spectra, the gamma particle count for each lane in the energy spectrum by the energy for the lane to obtain a unit energy count density spectrum.

The effective energy spectrum before normalization for Ba133 is shown in (a) and (b) in fig. 9.

As can be seen from the energy spectra in (a) and (b) of fig. 9, the energy spectra obtained by detecting the same radioactive substance in the same direction using the same detector needle are also different.

At this time, the two energy spectra need to be normalized.

Specifically, for each lane (e.g., lane 25) in the energy spectrum in (a) in fig. 9, the gamma particle count for that lane (e.g., the corresponding gamma particle count 29 for lane 25 in (a) in fig. 9) is divided by the energy for that lane (e.g., the energy for lane 25 is about 75) to obtain a count per energy for that lane, from which a count density spectrum per energy can be obtained (as in (c) in fig. 9).

Similar operations to those performed on the energy spectrum in (a) in fig. 9 are performed on the energy spectrum in (b) in fig. 9 to obtain a density spectrum of count per unit energy for the energy spectrum in (b) in fig. 9 (e.g., (d) in fig. 9).

Based on (c) and (d) in fig. 9, it can be seen that the two energy count density spectra obtained after normalization are closer.

In operation S803, the central processing unit 101 adds the count density spectra for unit energy for the effective energy spectrum to obtain a synthesized count density spectrum for unit energy.

In operation S805, for the synthesized unit energy count density spectrum, the central processing unit 101 multiplies, for each lane, the unit energy count corresponding to the lane by the energy for the lane to obtain a synthesized energy spectrum.

At this time, a composite spectrum for determining the category of the radioactive substance has been obtained (as shown in (e) in fig. 9).

As can be seen from (e) in fig. 9, the peak shapes of the four full energy peaks 80kev, 160kev, 194kev and 355kev in the synthesized energy spectrum for Ba133 are relatively clear, and the full energy peak area is improved, so that the accuracy of the subsequent nuclide identification can be greatly improved by using the energy spectrum.

The radioactive substance detection method is described above with reference to a block diagram. It will be understood by those skilled in the art that the various operations in the radioactive material detection method need not be performed in the order shown, and that multiple operations may be performed in parallel or substantially simultaneously, or in reverse order, or in any suitable order.

Fig. 10 schematically illustrates a block diagram of a radioactive material detection apparatus 1000 according to an embodiment of the present disclosure.

As shown in fig. 10, the radioactive material detection apparatus 1000 may include a plurality of detectors 1001, a screening module 1002, a combining module 1003, and a determining module 1004.

The plurality of detectors 1001 may be configured to detect objects with radioactive material to obtain a plurality of energy spectra for the radioactive material.

The filtering module 1002 may be configured to filter the plurality of energy spectra to filter out an effective energy spectrum from the plurality of energy spectra.

The combining module 1003 may be configured to combine the effective energy spectra to obtain a composite energy spectrum.

The determining module 1004 may be configured to determine the category of the radioactive material based on the composite energy spectrum.

In addition to the above plurality of detectors 1001, screening module 1002, merging module 1003 and determination module 1004, the radioactive substance detection apparatus 1000 may further include other modules for performing the above various operations accordingly.

For clarity and brevity, the respective modules and the corresponding operations performed therein are not described again.

The functionality of a plurality of modules according to embodiments of the present disclosure may be implemented in one module. One module according to the embodiments of the present disclosure may be implemented by being split into a plurality of modules. A module according to an embodiment of the present disclosure may be implemented at least in part as a hardware circuit, such as a Field Programmable Gate Array (FPGA), a Programmable Logic Array (PLA), a system on a chip, a system on a substrate, a system on a package, an Application Specific Integrated Circuit (ASIC), or may be implemented in any other reasonable manner of hardware or firmware by integrating or packaging circuits, or in any one of three implementations, software, hardware, and firmware, or in any suitable combination of any of them. Alternatively, modules according to embodiments of the present disclosure may be implemented at least in part as computer program modules that, when executed, may perform corresponding functions.

According to an embodiment of the present disclosure, at least one of the above modules may be implemented at least partially as a hardware circuit, such as a Field Programmable Gate Array (FPGA), a Programmable Logic Array (PLA), a system on a chip, a system on a substrate, a system on a package, an Application Specific Integrated Circuit (ASIC), or may be implemented in hardware or firmware by any other reasonable manner of integrating or packaging a circuit, or in any one of three implementations of software, hardware, and firmware, or in a suitable combination of any of them. Optionally, at least one of the above modules may be implemented at least partly as a computer program module, which when executed may perform a corresponding function.

Fig. 11 schematically illustrates a block diagram of an electronic device suitable for implementing the radioactive material detection method described above according to an embodiment of the present disclosure. The electronic device shown in fig. 11 is only an example, and should not bring any limitation to the functions and the scope of use of the embodiments of the present disclosure.

As shown in fig. 11, an electronic device 1100 according to an embodiment of the present disclosure includes a processor 1101, which can perform various appropriate actions and processes according to a program stored in a Read Only Memory (ROM)1102 or a program loaded from a storage section 1108 into a Random Access Memory (RAM) 1103. The processor 1101 may comprise, for example, a general purpose microprocessor (e.g., a CPU), an instruction set processor and/or associated chipset, and/or a special purpose microprocessor (e.g., an Application Specific Integrated Circuit (ASIC)), among others. The processor 1101 may also include on-board memory for caching purposes. The processor 1101 may comprise a single processing unit or a plurality of processing units for performing the different actions of the method flows according to the embodiments of the present disclosure.

In the RAM 1103, various programs and data necessary for the operation of the electronic device 1100 are stored. The processor 1101, the ROM 1102, and the RAM 1103 are connected to each other by a bus 1104. The processor 1101 performs various operations of the method flow according to the embodiments of the present disclosure by executing programs in the ROM 1102 and/or the RAM 1103. It is noted that the programs may also be stored in one or more memories other than the ROM 1102 and RAM 1103. The processor 801 may also perform various operations of method flows according to embodiments of the present disclosure by executing programs stored in the one or more memories.

Electronic device 1100 may also include input/output (I/O) interface 1105, input/output (I/O) interface 1105 also connected to bus 1104, according to an embodiment of the disclosure. Electronic device 1100 may also include one or more of the following components connected to I/O interface 1105: an input portion 1106 including a keyboard, mouse, and the like; an output portion 1107 including a signal output unit such as a Cathode Ray Tube (CRT), a Liquid Crystal Display (LCD), and a speaker; a storage section 1108 including a hard disk and the like; and a communication section 1109 including a network interface card such as a LAN card, a modem, or the like. The communication section 1109 performs communication processing via a network such as the internet. A driver 1110 is also connected to the I/O interface 1105 as necessary. A removable medium 1111 such as a magnetic disk, an optical disk, a magneto-optical disk, a semiconductor memory, or the like is mounted on the drive 1110 as necessary, so that a computer program read out therefrom is mounted into the storage section 1108 as necessary.

According to embodiments of the present disclosure, method flows according to embodiments of the present disclosure may be implemented as computer software programs. For example, embodiments of the present disclosure include a computer program product comprising a computer program embodied on a computer readable storage medium, the computer program containing program code for performing the method illustrated by the flow chart. In such an embodiment, the computer program may be downloaded and installed from a network through the communication portion 1109 and/or installed from the removable medium 1111. The computer program, when executed by the processor 1101, performs the above-described functions defined in the system of the embodiment of the present disclosure. The systems, devices, apparatuses, modules, units, etc. described above may be implemented by computer program modules according to embodiments of the present disclosure.

The present disclosure also provides a computer-readable storage medium, which may be contained in the apparatus/device/system described in the above embodiments; or may exist separately and not be assembled into the device/apparatus/system. The computer-readable storage medium carries one or more programs which, when executed, implement the method according to an embodiment of the disclosure.

According to embodiments of the present disclosure, the computer-readable storage medium may be a non-volatile computer-readable storage medium, which may include, for example but is not limited to: a portable computer diskette, a hard disk, a Random Access Memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), a portable compact disc read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing. In the present disclosure, a computer readable storage medium may be any tangible medium that can contain, or store a program for use by or in connection with an instruction execution system, apparatus, or device. For example, according to embodiments of the present disclosure, a computer-readable storage medium may include the ROM 1102 and/or the RAM 1103 and/or one or more memories other than the ROM 1102 and the RAM 1103 described above.

The flowchart and block diagrams in the figures illustrate the architecture, functionality, and operation of possible implementations of systems, methods and computer program products according to various embodiments of the present disclosure. In this regard, each block in the flowchart or block diagrams may represent a module, segment, or portion of code, which comprises one or more executable instructions for implementing the specified logical function(s). It should also be noted that, in some alternative implementations, the functions noted in the block may occur out of the order noted in the figures. For example, two blocks shown in succession may, in fact, be executed substantially concurrently, or the blocks may sometimes be executed in the reverse order, depending upon the functionality involved. It will also be noted that each block of the block diagrams or flowchart illustration, and combinations of blocks in the block diagrams or flowchart illustration, can be implemented by special purpose hardware-based systems which perform the specified functions or acts, or combinations of special purpose hardware and computer instructions.

Those skilled in the art will appreciate that various combinations and/or combinations of features recited in the various embodiments and/or claims of the present disclosure can be made, even if such combinations or combinations are not expressly recited in the present disclosure. In particular, various combinations and/or combinations of the features recited in the various embodiments and/or claims of the present disclosure may be made without departing from the spirit or teaching of the present disclosure. All such combinations and/or associations are within the scope of the present disclosure.

The embodiments of the present disclosure have been described above. However, these examples are for illustrative purposes only and are not intended to limit the scope of the present disclosure. Although the embodiments are described separately above, this does not mean that the measures in the embodiments cannot be used in advantageous combination. The scope of the disclosure is defined by the appended claims and equivalents thereof. Various alternatives and modifications can be devised by those skilled in the art without departing from the scope of the present disclosure, and such alternatives and modifications are intended to be within the scope of the present disclosure.

Claims

1. A method of radioactive material detection, comprising:

detecting an object with a radioactive substance with a plurality of detectors to obtain a plurality of energy spectra for the radioactive substance;

screening the plurality of energy spectrums to screen effective energy spectrums from the plurality of energy spectrums;

combining the effective energy spectrums to obtain a synthesized energy spectrum; and

determining a class of the radioactive material based on the composite energy spectrum.

2. The radioactive substance detection method according to claim 1, wherein the screening the plurality of energy spectra to screen an effective energy spectrum from the plurality of energy spectra includes:

selecting a detector from the plurality of detectors that is closest to the radioactive material based on the plurality of energy spectra produced by the plurality of detectors;

selecting an energy spectrum with the highest possibility that the irradiation on the radioactive substance is front irradiation from energy spectrums of detectors closest to the radioactive substance; and

and determining the energy spectrum with the highest possibility of irradiating the radioactive substance as front irradiation as the effective energy spectrum.

3. The method for detecting radioactive material according to claim 2, wherein selecting the detector closest to the radioactive material from the plurality of detectors includes:

calculating a gamma particle count rate for each detector of the plurality of detectors; and

the detector with the largest gamma particle count rate is determined to be the detector closest to the radioactive material.

4. The radioactive substance detection method according to claim 2, wherein selecting the energy spectrum with the highest probability that the irradiation with the radioactive substance is a front irradiation from the energy spectra of the detector closest to the radioactive substance includes:

determining a trend of gamma particle count rates for each of the energy spectra of the detector nearest to the radioactive material; and

and determining the energy spectrum with the trend of the gamma particle counting rate meeting a preset rule as the energy spectrum with the highest possibility of irradiating the radioactive substance with the front surface.

5. The radioactive substance detection method according to claim 1, wherein, before the effective energy spectra are combined, the following operations are further performed:

and normalizing the effective energy spectrum.

6. The radioactive substance detection method according to claim 5, wherein normalizing the effective energy spectrum includes:

for each of the effective energy spectra, dividing the gamma particle count for each pass in the energy spectrum by the energy for that pass to obtain a unit energy count density spectrum;

adding the energy count density spectra for the effective energy spectra to obtain a synthesized energy count density spectrum; and

for the synthesized energy count density spectrum, the energy count for each track is multiplied by the energy for that track to obtain the synthesized energy spectrum.

7. A radioactive substance detection apparatus, comprising:

a plurality of detectors configured to detect objects with radioactive material to obtain a plurality of energy spectra for the radioactive material;

a screening module configured to screen the plurality of energy spectra to screen an effective energy spectrum from the plurality of energy spectra;

a merging module configured to merge the effective energy spectra to obtain a composite energy spectrum; and

a determination module configured to determine a category of the radioactive material based on the composite energy spectrum.

8. An electronic device, comprising:

one or more processors; and

a memory for storing one or more programs,

wherein the one or more programs, when executed by the one or more processors, cause the one or more processors to implement the method of any of claims 1-7.

9. A computer readable storage medium having stored thereon executable instructions which, when executed by a processor, cause the processor to carry out the method of any one of claims 1 to 7.