A method and apparatus for identifying a nuclide

Abstract

The application provides a nuclide identification method and device, comprising: obtaining gamma spectrum data of a target radioactive source; determining whether other characteristic peaks except for specified characteristic peaks are contained in characteristic peaks of the gamma spectrum data; if yes, determining a first peak area corresponding to the other characteristic peaks and a second peak area of the specified characteristic peaks according to the gamma spectrum data; determining a total area of the specified characteristic peaks contributed by all nuclides of the target radioactive source according to the first peak area and a peak branch ratio of each first nuclide; determining whether the second nuclide having only the specified energy peak value is contained in the target radioactive source according to the second peak area and the total area; if yes, determining the second nuclide in the target radioactive source through half-life measurement; and determining the nuclide composition of the target radioactive source according to the first nuclide and the second nuclide. The method can identify the heavy peak by setting the verification condition, and then determine the nuclide composition, so that the technical problem of nuclide missing identification can be relieved.

Description

Technical Field

[0001] This invention relates to the field of energy spectrum analysis technology, and in particular to a method and apparatus for nuclide identification. Background Technology

[0002] Energy dispersive spectroscopy (EDS) involves irradiating or bombarding a sample with a single light source or electron beam, exciting electrons within the sample to emit. The yield (intensity) of these electrons and their energy distribution are then measured to obtain relevant information. Since 2021, when the my country Atomic Energy Authority, in conjunction with the Ministry of Science and Technology and other departments, officially released the "Medium- and Long-Term Development Plan for Medical Isotopes (2021-2035)," it has marked a period of explosive growth for nuclear medicine in my country. Medical isotopes are generally divided into diagnostic and therapeutic categories. Both types of drugs used in vivo generally require low toxicity of the radionuclide and its decay products, easy clearance from the body to reduce unnecessary damage, and high specific activity and radioactive purity. It is worth noting that monitoring and analysis of radionuclides are necessary throughout the entire medical isotope industry chain (production, use, and disposal). During the production of radiopharmaceuticals, quality testing and radionuclide purity analysis are required; after use and before discharge, radioactive waste must be monitored using spectral analysis software to ensure compliance with emission standards. In conclusion, developing an energy dispersive spectroscopy (EDS) method capable of analyzing radioisotopes in nuclear medicine has significant practical implications.

[0003] In current energy spectrum analysis, a single peak in the spectrum is generally considered to be a single nuclide. However, when there are duplicate peaks, a single peak is actually produced by the combined action of multiple nuclides. If a single peak is still identified as a single nuclide, it will lead to the omission and misidentification of some nuclides, resulting in low accuracy of nuclide identification. Summary of the Invention

[0004] In view of this, the purpose of the present invention is to provide a nuclide identification method and a nuclide identification device to improve the accuracy of analysis results.

[0005] In a first aspect, embodiments of the present invention provide a method for identifying nuclides, the method comprising:

[0006] Acquire gamma-ray spectrum data of the target radioactive source; wherein the characteristic peaks of the gamma-ray spectrum data contain specified characteristic peaks, and the specified characteristic peaks have specified energy peak values;

[0007] Determine whether the characteristic peaks of the γ-ray spectrum data contain other characteristic peaks besides the specified characteristic peak;

[0008] If so, determine the first peak area corresponding to the other characteristic peak and the second peak area of ​​the specified characteristic peak based on the γ-ray spectrum data; each other characteristic peak corresponds to a first nuclide;

[0009] determining a total area of the specified characteristic peak contributed by all the nuclides of the target radioactive source according to the first peak area and the peak branching ratio of each of the first nuclides;

[0010] determining whether the target radioactive source contains a second nuclide having only the specified energy peak value according to the second peak area and the total area;

[0011] if yes, determining the second nuclide in the target radioactive source by half-life measurement;

[0012] determining the nuclide composition of the target radioactive source according to the first nuclides and the second nuclide.

[0013] As an implementable manner, the step of determining a total area of the specified characteristic peak contributed by all the nuclides of the target radioactive source according to the first peak area and the peak branching ratio of each of the first nuclides comprises:

[0014] the total area of the specified characteristic peak is calculated by the following formula:

[0015] S P ;

[0016] wherein S i a is the first peak area of the i-th nuclide of the target radioactive source; E i a is the peak branching ratio of other characteristic peaks of the i-th nuclide of the target radioactive source; E i p is the peak branching ratio of the specified characteristic peak of the i-th nuclide of the target radioactive source.

[0017] As an implementable manner, the step of determining whether the target radioactive source contains a second nuclide having only the specified energy peak value according to the second peak area and the total area comprises:

[0018] calculating an area error value according to the second peak area and the total area;

[0019] judging whether the area error value is greater than a preset discrimination threshold value;

[0020] if yes, determining that the target radioactive source contains the second nuclide having only the specified energy peak value; otherwise, determining that the target radioactive source does not contain the second nuclide having only the specified energy peak value.

[0021] As an implementable manner, the area error value is determined by the following formula:

[0022] ;

[0023] wherein Mo is the area error value, S T is the second peak area, S p is the total area.

[0024] As an implementable manner, after the step of determining that the target radioactive source does not contain the second nuclide with only the specified energy peak, the method further comprises:

[0025] determining the first nuclide as the nuclide composition of the target radioactive source.

[0026] As an implementable manner, the step of determining the second nuclide in the target radioactive source through half-life measurement comprises:

[0027] continuously performing half-life measurement on the target radioactive source twice for a preset time length to obtain first energy spectrum data and second energy spectrum data;

[0028] based on the first energy spectrum data and the second energy spectrum data respectively, calculating the area of the specified characteristic peak contributed by the second nuclide to correspondingly obtain a first contribution area and a second contribution area;

[0029] based on the first contribution area and the second contribution area, calculating the half-life of the second nuclide;

[0030] determining the second nuclide in the target radioactive source according to the half-life.

[0031] As an implementable manner, the step of calculating the half-life of the second nuclide based on the first contribution area and the second contribution area comprises:

[0032] calculating the half-life of the second nuclide through the following formula:

[0033] ;

[0034] ;

[0035] N1 t =|S T 1 -S p 1 |;

[0036] N2 t =|S T 2 -S p 2 |;

[0037] wherein, T 1 / 2 is the half-life of the second nuclide; λ is the decay constant; t is the preset time length; N1 tis the first contribution area; N2 t is the second contribution area; S T 1 is the second peak area calculated based on the first energy spectrum data; S p 1 is the total area of the specified characteristic peak calculated based on the first energy spectrum data; S T 2 is the second peak area calculated based on the second energy spectrum data; S p 2 is the total area of the specified characteristic peak calculated based on the second energy spectrum data.

[0038] As an implementable manner, after the step of judging whether the characteristic peaks of the gamma spectrum data contain other characteristic peaks in addition to the specified characteristic peak, the method further comprises:

[0039] If it is judged that the characteristic peaks of the gamma spectrum data do not contain other characteristic peaks in addition to the specified characteristic peak, determining the third nuclide in the target radioactive source through half-life measurement;

[0040] determining the third nuclide as the nuclide composition of the target radioactive source.

[0041] As an implementable manner, the specified characteristic peak is a positron annihilation peak, and the specified energy peak value is 0.511 Mev.

[0042] The second aspect of the application provides a nuclide identification device, which comprises:

[0043] a gamma spectrum data acquisition module, configured to acquire gamma spectrum data of a target radioactive source; wherein the characteristic peaks of the gamma spectrum data contain a specified characteristic peak, and the specified characteristic peak has a specified energy peak value;

[0044] a first judging module, configured to judge whether the characteristic peaks of the gamma spectrum data contain other characteristic peaks in addition to the specified characteristic peak;

[0045] a first calculating module, configured to, if yes, determine, according to the gamma spectrum data, a first peak area corresponding to the other characteristic peaks and a second peak area of the specified characteristic peak; each of the other characteristic peaks corresponds to a first nuclide;

[0046] a second calculating module, configured to determine, according to the first peak area and a peak branch ratio of each of the first nuclides, a total area of the specified characteristic peak contributed by all nuclides of the target radioactive source;

[0047] a second judging module, configured to determine, according to the second peak area and the total area, whether the target radioactive source contains a second nuclide having only the specified energy peak value;

[0048] a third calculating module, configured to: if yes, determining the second nuclide in the target radioactive source through half-life measurement;

[0049] a nuclide composition determining module, configured to determine a nuclide composition of the target radioactive source according to the first nuclide and the second nuclide.

[0050] The embodiment of the present application brings the following beneficial effects:

[0051] The present application provides a nuclide identification method and device, the method comprising: obtaining gamma spectrum data of a target radioactive source; wherein the characteristic peaks of the gamma spectrum data contain a specified characteristic peak, and the specified characteristic peak has a specified energy peak value; determining whether the characteristic peaks of the gamma spectrum data contain other characteristic peaks in addition to the specified characteristic peak; if yes, determining a first peak area corresponding to the other characteristic peaks and a second peak area of the specified characteristic peak according to the gamma spectrum data; each of the other characteristic peaks corresponds to a first nuclide; determining a total area of the specified characteristic peak contributed by all nuclides of the target radioactive source according to the first peak area and a peak branch ratio of each of the first nuclides; determining whether the target radioactive source contains a second nuclide having only the specified energy peak value according to the second peak area and the total area; if yes, determining the second nuclide in the target radioactive source through half-life measurement; and determining a nuclide composition of the target radioactive source according to the first nuclide and the second nuclide.

[0052] The present application sets verification conditions to determine whether there is a heavy peak. In the case of a heavy peak, the absolute value of the difference between the second area of the other characteristic peaks except the specified characteristic peak and the total area of the specified characteristic peak of all nuclides is taken as the pure specified characteristic peak nuclide contribution, and through two consecutive measurements of the same length, the nuclide half-life is calculated according to the contribution area of two times, and then the nuclide composition of the radioactive source is determined according to the half-life table, which can avoid mistaking the peak position under the heavy peak condition as a single nuclide, leading to missed identification of the nuclide, thereby improving the nuclide identification accuracy.

[0053] Other features and advantages of the present application will be set forth in the following description, and in part will become apparent to those skilled in the art from the description, or can be learned by practice of the present application. The objects and other advantages of the present application will be realized and achieved by the structure particularly pointed out in the description, claims and drawings.

[0054] In order to make the above-mentioned objects, features and advantages of the present application more obvious and easy to understand, the following preferred embodiments are specifically described below, and the accompanying drawings are described in detail as follows. BRIEF DESCRIPTION OF DRAWINGS

[0055] In order to more clearly illustrate the specific embodiments of the present application or the technical solutions in the prior art, the following will briefly introduce the drawings needed to be used in the specific embodiments or prior art description. Obviously, the drawings described below are some embodiments of the present application, and other drawings can also be obtained by those skilled in the art without creative labor on the basis of these drawings.

[0056] Figure 1 A flow chart of a nuclide identification method provided for the embodiment 1 of the present application;

[0057] Figure 2 A flow chart of another nuclide identification method provided for the embodiment 2 of the present application;

[0058] Figure 3 A flow chart of the step of determining the second nuclide in the target radioactive source by half-life measurement in the nuclide identification method provided for the embodiment 2 of the present application;

[0059] Figure 4 A flow chart of another nuclide identification method provided for the embodiment 3 of the present application;

[0060] Figure 5 A schematic diagram of the composition structure of the nuclide identification device provided by the present application.

[0061] Reference signs:

[0062] 10 - γ spectrum data acquisition module; 20 - first judging module; 30 - first calculating module; 40 - second calculating module; 50 - second judging module; 60 - third calculating module; 70 - nuclide composition determining module. DETAILED DESCRIPTION

[0063] In order to make the purpose, technical solutions and advantages of the embodiments of the present application more clear, the technical solutions of the present application will be described clearly and completely below in combination with the drawings. Obviously, the described embodiments are some embodiments of the present application, but not all the embodiments. Based on the embodiments in the present application, all the other embodiments obtained by those skilled in the art without creative labor belong to the protection scope of the present application.

[0064] In order to facilitate the understanding of the present embodiment, the technical terms designed in the present application will be briefly introduced below.

[0065] Spectrum refers to the distribution curve of the count rate with the particle energy after the pulse amplitude is scaled. The output pulse of the ionization chamber is amplified by the preamplifier and linear pulse amplifier, and then input into the single-channel or multi-channel pulse analyzer to measure the distribution curve of the counter rate with the pulse amplitude. This curve becomes the pulse spectrum. Spectrum is applied in many fields such as medicine, aerospace, nuclear research, etc.

[0066] Spectrum analysis is to use a single light source or electron beam to irradiate or bombard the sample, so that the electrons in the sample are excited and emitted, and then the distribution of the yield (intensity) of these electrons with respect to their energy is measured to obtain relevant information.

[0067] After introducing the technical terms related to the present application, next, the application scenarios and design ideas of the embodiments of the present application are simply introduced.

[0068] Spectrum analysis can be performed by bombarding the sample with an electron beam of a certain energy, and the electrons in the surface layer of the sample are ionized. By performing qualitative and quantitative analysis on the sample, it is obtained that the electron beam is composed of which nuclides. Under normal circumstances, different characteristic peaks and peak values corresponding to the characteristic peaks are obtained according to spectrum analysis.

[0069] In the spectrum analysis process of the related art, a single peak position in the spectrum is generally considered to be a single nuclide. When there is a heavy peak, in fact, a peak position is generated by the joint action of multiple nuclides. If the single peak position is still identified as a single nuclide, it will lead to missed identification and misidentification of some nuclides, and the nuclide identification accuracy is low.

[0070] Based on this, the purpose of the present application is to provide a nuclide identification method to improve the nuclide identification accuracy. The device to which the nuclide identification method is applied further includes a processor, and the processor is used to execute the nuclide identification method to identify the target nuclide composition.

[0071] Embodiment 1

[0072] In combination with Figure 1 the present application, the embodiments of the present application provide a nuclide identification method, which includes the following steps:

[0073] S110, the processor acquires the gamma spectrum data of the target radioactive source; wherein the characteristic peaks of the gamma spectrum data include a specified characteristic peak, and the specified characteristic peak has a specified energy peak value.

[0074] S120, the processor determines that the characteristic peaks of the gamma spectrum data include other characteristic peaks in addition to the specified characteristic peak.

[0075] S130, the processor determines the first peak area corresponding to the other characteristic peaks and the second peak area of the specified characteristic peak according to the gamma spectrum data; each other characteristic peak corresponds to a first nuclide.

[0076] S140, the processor determines the total area of the specified characteristic peak contributed by all nuclides of the target radioactive source according to the first peak area and the peak branch ratio of each first nuclide.

[0077] S150, the processor determines that the target radioactive source contains a second nuclide having only the specified energy peak value according to the second peak area and the total area.

[0078] S160, the processor determines the second nuclide in the target radioactive source through the half-life measurement.

[0079] S170, the processor determines the nuclide composition of the target radioactive source according to the first nuclide and the second nuclide.

[0080] In the embodiment of the present application, the determination condition for confirming the existence of the heavy peak is set, and in the case where the heavy peak exists, the second nuclide corresponding to the heavy peak position is inversely deduced through the half-life measurement, and finally the nuclide composition of the target radioactive source is determined according to the first nuclide and the second nuclide. In this way, the heavy peak position is assigned to multiple nuclides, which can avoid missing identification and improve the accuracy of nuclide identification.

[0081] In step S110 of the embodiment, after obtaining the full spectrum and calibrating the full spectrum by measuring the energy-channel relationship of the standard source, the energy calibration curve is obtained. Then, according to the energy calibration curve, the characteristic peak in the full spectrum and the energy peak value corresponding to the characteristic peak are found. Under the premise that the characteristic peak contains the specified characteristic peak, the specified energy peak value of the specified characteristic peak is obtained.

[0082] In step S120 of the embodiment, it is determined whether there is a characteristic peak other than the specified characteristic peak by judging whether the energy peak value of each characteristic peak has a value other than the specified energy peak value.

[0083] In step S130 of the embodiment, in the case where it is determined in step S120 that there is a characteristic peak other than the specified characteristic peak, the first peak area corresponding to the other characteristic peak and the second peak area of the specified characteristic peak are determined according to the existing technical means of energy spectrum quantitative analysis.

[0084] In step S150 of the embodiment, it is determined whether the target radioactive source contains the second nuclide with the specified energy peak value by judging the size relationship between the absolute value of the difference between the second peak area and the total area and the preset discrimination threshold. Specifically, in the case where the absolute value of the difference between the second peak area and the total area is less than the preset discrimination coefficient, it is determined that the target radioactive source contains the second nuclide with the specified energy peak value. Otherwise, it is determined that the target radioactive source does not contain the second nuclide with the specified energy peak value.

[0085] In step S160 of the embodiment, in the case where it is determined in step S150 that the target radioactive source contains the second nuclide with the specified energy peak value, the second nuclide in the target radioactive source is determined through the half-life measurement inverse deduction.

[0086] Since 2021, China's atomic energy agency has officially released the 'Medical Isotope Medium and Long-term Development Plan (2021-2035)' together with the Ministry of Science and Technology and other departments, marking that China's nuclear medicine will usher in a development stage of gushing. Medical isotopes can be generally divided into diagnostic and therapeutic categories. Generally, the radionuclides and their decay products used in the body are required to be less toxic and easily cleared from the body to reduce unnecessary damage to the body, with high specific activity and radioactivity purity. It is worth noting that in the whole industry chain of medical isotopes (production, use, and scrap), radioactive isotopes need to be monitored and analyzed. In the production process of radiopharmaceuticals, quality testing and radionuclide purity analysis of the drugs are required; before discharge, spectrum analysis software needs to be used to monitor radioactive waste to ensure that it meets the discharge standards. Common radioactive isotopes such as: 11 C、 13 N、 15 O、 18 F are only positive electron annihilation peaks (0.511 peaks). In this embodiment, the medical isotope identification process is taken as an example to illustrate: in this embodiment, the specified characteristic peak is the positive electron annihilation peak (0.511 peak).

[0087] In the spectrum analysis process in the related art, a peak position is considered as a single nuclide. However, this analysis method can lead to missed identification and misidentification of some nuclides, so that the results of nuclide activity and purity measurement in the subsequent nuclide analysis calculation process deviate from the true value.

[0088] In this embodiment, the gamma spectrum data of the target radioactive source is obtained; wherein the characteristic peaks of the gamma spectrum data include a positive electron annihilation peak (0.511 peak), and the positive electron annihilation peak has a specified energy peak value, that is, 0.511 Mev.

[0089] It is judged whether the characteristic peaks of the spectrum data include other characteristic peaks in addition to the positive electron annihilation peak (0.511 peak).

[0090] According to the gamma spectrum data, the first peak area S i a and the second peak area S T of the positive electron annihilation peak are determined; each other characteristic peak corresponds to a nuclide. For example, the energy peak values of the other characteristic peaks are 1.116, 0.723, and 0.368. According to the preset mapping relationship, the nuclides corresponding to the energy peak values of each other characteristic peak in the preset chart are found.

[0091] After checking the chart, it can be known that the nuclide corresponding to 1.116 is 65 Zn; the nuclide corresponding to 0.723 is 124 I; and the nuclide corresponding to 0.368 is 200 Tl.

[0092] The preset mapping relationship table is shown in Table 1.

[0093] Table 1: Preset mapping relationship table

[0094]

[0095] Then, the total area of the positron annihilation peak of all the nuclide contributions of the target radioactive source is calculated. As an implementable manner, the total area of the specified characteristic peak is calculated by the following formula:

[0096] S P ;

[0097] Wherein, n is the total number of nuclides; S i a is the first peak area of the i-th nuclide of the target radioactive source; E i a is the peak branching ratio of the other characteristic peak of the i-th nuclide of the target radioactive source; E i p is the peak branching ratio of the specified characteristic peak of the i-th nuclide of the target radioactive source. In this embodiment, the specified characteristic peak is the positron annihilation peak.

[0098] As an implementable manner, the step of determining whether the target radioactive source contains the second nuclide with only the specified energy peak value according to the second peak area and the total area in step S150 comprises:

[0099] According to the second peak area and the total area, an area error value is calculated. Specifically, the area error value is calculated by the following formula:

[0100] ;

[0101] Wherein, S T is the second peak area; Sp is the total area of the specified characteristic peak.

[0102] Then, M o is compared with a preset discrimination threshold value. In the case that M o is greater than or equal to the preset discrimination threshold value, it is determined that the target radioactive source contains the second nuclide with only the specified energy peak value. The preset discrimination threshold value is 9% to 10.2%. Then, the second nuclide contained in the target radioactive source is determined according to the preset mapping relationship by the half-life measurement result. Finally, the nuclide composition of the target radioactive element is determined. For example, the half-life result is calculated to be 569 min. According to the mapping relationship table 1, the second nuclide is 66 Ga. Combined with the above distance, the nuclide composition of the target radioactive element is determined to be 65 Zn,124 I、 200 Tl and 66 Ga.

[0103] Embodiment 2

[0104] The embodiment of the present application provides another nuclide identification method, which combines the nuclide identification method of the embodiment of the present application with the nuclide identification method of the embodiment of the present application. Figure 2 As shown in the figure, the nuclide identification method comprises the following steps:

[0105] S210, a processor acquires γ energy spectrum data of a target radioactive source; wherein a characteristic peak of the γ energy spectrum data comprises a specified characteristic peak, and the specified characteristic peak has a specified energy peak value.

[0106] S220, the processor determines that the characteristic peak of the γ energy spectrum data comprises other characteristic peaks in addition to the specified characteristic peak.

[0107] S230, the processor determines, according to the γ energy spectrum data, a first peak area corresponding to each of the other characteristic peaks and a second peak area of the specified characteristic peak; each of the other characteristic peaks corresponds to a first nuclide.

[0108] S240, the processor determines, according to the first peak area and a peak branch ratio of each of the first nuclides, a total area of the specified characteristic peak contributed by all nuclides of the target radioactive source.

[0109] S250, the processor determines, according to the second peak area and the total area, whether the target radioactive source comprises a second nuclide having only the specified energy peak value.

[0110] If yes, step S260 is performed.

[0111] If no, step S280 is performed.

[0112] S260, the processor determines the second nuclide in the target radioactive source through half-life measurement.

[0113] S270, the processor determines a nuclide composition of the target radioactive source according to the first nuclide and the second nuclide.

[0114] S280, the processor determines the first nuclide as the nuclide composition of the target radioactive source.

[0115] In the embodiment, according to the determination condition, it is determined whether the area error value is less than the preset discrimination threshold value; when the area error value is less than the preset discrimination threshold value, it is determined that the target radioactive source does not comprise the second nuclide having the specified energy peak value. At this time, the first nuclide is determined as the nuclide composition of the target radioactive source. Otherwise, it is determined that the target radioactive source comprises the second nuclide having the specified energy peak value. At this time, the second nuclide is obtained through half-life back calculation, and the combination of the first nuclide and the second nuclide is determined as the nuclide composition of the target radioactive source.

[0116] In the embodiment, it is first judged whether other characteristic peaks except the specified characteristic peak are contained, and in the case that other characteristic peaks are contained, it is continuously judged whether the second nuclide with the specified energy peak value is contained, and the specific composition of the target radioactive source is determined according to the judgment result. In this way, nuclide missing recognition can be avoided, and the nuclide recognition accuracy is improved.

[0117] As an implementable manner, in combination with Figure 3 the embodiment, the step S260 includes the following steps:

[0118] S261, the processor performs half-life measurement on the target radioactive source for two times continuously according to a preset time length, and obtains first energy spectrum data and second energy spectrum data;

[0119] S262, the processor calculates the area of the specified characteristic peak contributed by the second nuclide based on the first energy spectrum data and the second energy spectrum data respectively, and correspondingly obtains a first contribution area and a second contribution area;

[0120] S263, the processor calculates the half-life of the second nuclide based on the first contribution area and the second contribution area;

[0121] S264, the processor determines the second nuclide in the target radioactive source according to the half-life.

[0122] In the step S261 of the embodiment, the preset time length is 8-12 minutes, and through multiple experiments, it is found that the measurement effect is best when the preset time length is 10 minutes, and in the embodiment, the preset time length is 10 minutes.

[0123] In the step S262 of the embodiment, the area of the specified characteristic peak contributed by the second nuclide is calculated, and the corresponding first contribution area and the second contribution area are obtained, and the specific calculation method is as follows:

[0124] The contribution area is calculated by the following formula: N m t =|S T m -S P m |;

[0125] Wherein, N m t is the mth contribution area, t is the preset time length, S T m is the second peak area calculated based on the mth energy spectrum data; and S P m is the total area of the specified characteristic peak calculated based on the mth energy spectrum data.

[0126] In the embodiment, the two contribution areas are calculated, and N1 t and N2t .

[0127] As one feasible approach, step S263 is based on the first contributing area N1 t Second contribution area N1 t Calculate the half-life T of the second nuclide. 1 / 2 The steps include:

[0128] Calculate the half-life of the second nuclide using the following formula:

[0129] ;

[0130] ;

[0131] N1 t =|S T 1 -S p 1 |;

[0132] N2 t =|S T 2 -S p 2 |;

[0133] Among them, T 1 / 2 The half-life of the second nuclide; λ is the decay constant; t is the preset duration; N1 t For one contributing area; N2 t The second contributing area; S T 1 S is the area of ​​the second peak calculated based on the first energy spectrum data. p 1 S represents the total area of ​​the specified characteristic peaks calculated based on the first energy spectrum data; T 2 S is the area of ​​the second peak calculated based on the second energy spectrum data. p 2 The total area of ​​the specified characteristic peak is calculated based on the second energy spectrum data.

[0134] In step S264 of this embodiment, after determining the half-life of the second nuclide, the second nuclide can be derived in reverse by consulting a chart based on a preset mapping relationship. For example, the half-life T is calculated. 1 / 2 =788.4min; Refer to charts and T 1 / 2 =788.4min corresponds to the second nuclide. 123 I.

[0135] Example 3

[0136] Combination Figure 4As shown, the embodiment of the present application provides a nuclide identification method, comprising the following steps:

[0137] S410, the processor acquires the gamma spectrum data of the target radioactive source; wherein the characteristic peaks of the gamma spectrum data contain a specified characteristic peak, and the specified characteristic peak has a specified energy peak value.

[0138] S420, the processor determines whether the characteristic peaks of the gamma spectrum data contain other characteristic peaks in addition to the specified characteristic peak.

[0139] If yes, step S430 is executed.

[0140] If no, step S480 is executed

[0141] S430, the processor determines the first peak area corresponding to the other characteristic peaks and the second peak area of the specified characteristic peak according to the gamma spectrum data; each other characteristic peak corresponds to a first nuclide.

[0142] S440, the processor determines the total area of the specified characteristic peak contributed by all nuclides of the target radioactive source according to the first peak area and the peak branch ratio of each first nuclide.

[0143] S450, the processor determines that the target radioactive source contains a second nuclide having only the specified energy peak value according to the second peak area and the total area.

[0144] S460, the processor determines the second nuclide in the target radioactive source through half-life measurement.

[0145] S470, the processor determines the nuclide composition of the target radioactive source according to the first nuclide and the second nuclide.

[0146] S480, the processor determines a third nuclide in the target radioactive source through half-life measurement.

[0147] S490, the processor determines the third nuclide as the nuclide composition of the target radioactive source.

[0148] In the case where the embodiment of the present application determines that the characteristic peaks of the gamma spectrum data do not contain other characteristic peaks in addition to the specified characteristic peak, the total area of the specified characteristic peak is calculated, and then the third nuclide in the target radioactive source is determined through half-life measurement according to the preset mapping relationship to obtain the nuclide composition of the target radioactive source. In this embodiment, first, it is determined whether other characteristic peaks are contained, and if no other characteristic peaks are contained, it indicates that the nuclides of the target radioactive source are composed of only the nuclides containing the specified characteristic peak. In combination with the example in embodiment 1, taking medical nuclide identification as an example, the specified characteristic peak is the positron annihilation peak, and the nuclides containing only the specified characteristic peak are: 11 C、 13 N、 15 O、 18F. At this time, in order to more accurately determine the specific nuclide composition and calculate the half-life, for example, the half-life is calculated to be 10 min, then according to the preset corresponding relationship (Table 1), the nuclide can be reversely deduced to contain 13 N.

[0149] In combination Figure 5 As shown in the second aspect of the present application provides a kind of nuclide identification device, the device comprises:

[0150] The gamma spectrum data acquisition module 10 is used to obtain the gamma spectrum data of the target radioactive source;Wherein, the characteristic peak of the gamma spectrum data contains a specified characteristic peak, and the specified characteristic peak has a specified energy peak value;

[0151] The first judging module 20 is used to determine whether the characteristic peak of the gamma spectrum data contains other characteristic peaks except the specified characteristic peak;

[0152] The first calculating module 30 is used to determine the first peak area corresponding to the other characteristic peaks and the second peak area of the specified characteristic peak according to the gamma spectrum data if yes;Each other characteristic peak corresponds to a first nuclide;

[0153] The second calculating module 40 is used to determine the total area of the specified characteristic peak contributed by all nuclides of the target radioactive source according to the first peak area and the peak branch ratio of each first nuclide;

[0154] The second judging module 50 is used to determine whether the second nuclide with only the specified energy peak value is contained in the target radioactive source according to the second peak area and the total area;

[0155] The third calculating module 60 is used to determine the second nuclide in the target radioactive source by half-life measurement if yes;

[0156] The nuclide composition determining module 70 is used to determine the nuclide composition of the target radioactive source according to the first nuclide and the second nuclide.

[0157] Those skilled in the art can clearly understand that, for the convenience and brevity of description, the specific working process of the above-described system and device can refer to the corresponding process in the foregoing method embodiments, which will not be described here.

[0158] In addition, in the description of the embodiments of the present application, unless otherwise explicitly specified and limited, the terms "mounting", "connecting", "connecting" should be understood broadly, for example, it can be fixedly connected, or it can be detachably connected, or integrally connected;It can be mechanically connected, or it can be electrically connected;It can be directly connected, or it can be indirectly connected through an intermediate medium, or it can be the communication inside two elements. For those skilled in the art, the specific meaning of the above terms in the present application can be understood according to the specific circumstances.

[0159] If the functions are realized in the form of software function units and sold or used as independent products, they can be stored in a computer readable storage medium. Based on this understanding, the technical solutions of the present application or the parts of the present application that essentially contribute to the prior art or the parts of the technical solutions can be embodied in the form of software products. The computer software product is stored in a storage medium and includes a plurality of instructions for causing a computer device (which can be a personal computer, a server, or a network device, etc.) to execute all or part of the steps of the method described in the various embodiments of the present application. The aforementioned storage medium includes: a U disk, a mobile hard disk, a read-only memory (ROM, Read-Only Memory), a random access memory (RAM, Random Access Memory), a magnetic disk or an optical disk, and various media that can store program codes.

[0160] In the description of the present application, it should be noted that the terms "center", "upper", "lower", "left", "right", "vertical", "horizontal", "inner", "outer" and the like indicate the orientation or positional relationship based on the orientation or positional relationship shown in the drawings, and are only for the purpose of facilitating the description of the present application and simplifying the description, and do not indicate or imply that the devices or elements referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore cannot be understood as limiting the present application. In addition, the terms "first", "second", "third" are only for the purpose of description, and cannot be understood as indicating or implying relative importance.

[0161] Finally, it should be noted that: the above embodiments are only specific embodiments of the present application, which are used to illustrate the technical solutions of the present application, and are not limited thereto, the protection scope of the present application is not limited thereto, although the present application has been described in detail with reference to the foregoing embodiments, those skilled in the art should understand that any person skilled in the art within the technical range disclosed by the present application can modify or easily think of changes to the technical solutions recorded in the foregoing embodiments, or make equivalent replacement to part of the technical features; and these modifications, changes or replacements do not make the corresponding technical solutions deviate from the spirit and scope of the technical solutions of the embodiments of the present application, and should be covered within the protection scope of the present application. Therefore, the protection scope of the present application should be subject to the protection scope of the claims.

Claims

1. A method of nuclide identification, characterized by, The method comprises: acquiring gamma spectrum data of a target radioactive source; wherein characteristic peaks of the gamma spectrum data include a specified characteristic peak having a specified energy peak value; determining whether the characteristic peaks of the gamma spectrum data include other characteristic peaks in addition to the specified characteristic peak; if yes, determining, according to the gamma spectrum data, a first peak area corresponding to the other characteristic peaks and a second peak area of the specified characteristic peak; each of the other characteristic peaks corresponds to a first nuclide; determining, according to the first peak area and a peak branch ratio of each of the first nuclides, a total area of the specified characteristic peak contributed by all nuclides of the target radioactive source; determining, according to the second peak area and the total area, whether the target radioactive source includes a second nuclide having only the specified energy peak value; if yes, continuously performing half-life measurement on the target radioactive source twice for a preset time length to obtain first and second spectrum data; based on the first and second spectrum data respectively, calculating areas of the specified characteristic peak contributed by the second nuclide to obtain first and second contribution areas; based on the first and second contribution areas, calculating a half-life of the second nuclide; and determining the second nuclide in the target radioactive source according to the half-life; determining a nuclide composition of the target radioactive source according to the first and second nuclides; wherein the step of determining, according to the first peak area and a peak branch ratio of each of the first nuclides, a total area of the specified characteristic peak contributed by all nuclides of the target radioactive source comprises: calculating the total area of the specified characteristic peak by the following formula: S P ； wherein n is the total number of nuclides; S i a is the peak area of the i-th nuclide of the target radioactive source; E i a is the peak branch ratio of the other characteristic peak of the i-th nuclide of the target radioactive source; E i p is the peak branch ratio of the specified characteristic peak of the i-th nuclide of the target radioactive source.

2. The nuclide identification method according to claim 1, characterized by, the step of determining, according to the second peak area and the total area, whether the target radioactive source includes a second nuclide having only the specified energy peak value comprises: calculating an area error value according to the second peak area and the total area; determining whether the area error value is greater than a preset discrimination threshold; if yes, determining that the target radioactive source includes the second nuclide having only the specified energy peak value; otherwise, determining that the target radioactive source does not include the second nuclide having only the specified energy peak value.

3. The nuclide identification method according to claim 2, characterized by, the area error value is determined by the following formula: ； wherein M o is the area error value, S T is the second peak area, S p is the total area.

4. The nuclide identification method according to claim 2, characterized by, after the step of determining that the target radioactive source does not include the second nuclide having only the specified energy peak value, the method further comprises: determining the first nuclide as the nuclide composition of the target radioactive source.

5. The nuclide identification method according to claim 1, characterized by, the step of calculating, based on the first and second contribution areas, the half-life of the second nuclide comprises: calculating the half-life of the second nuclide by the following formula: ； ； N1 t =|S T 1 -S p 1 |; N2 t =|S T 2 -S p 2 |; wherein T 1 / 2 is the half-life of the second nuclide; λ is the decay constant; t is the preset time length; N1 t is the first contribution area; N2 t is the second contribution area; S T 1 is the second peak area calculated based on the first energy spectrum data, S p 1 is the total area of the specified characteristic peak calculated based on the first energy spectrum data; S T 2 is the second peak area calculated based on the second energy spectrum data, S p 2 is the total area of the specified characteristic peak calculated based on the second energy spectrum data.

6. The nuclide identification method according to claim 1, characterized by, after the step of determining whether the characteristic peaks of the gamma spectrum data include other characteristic peaks in addition to the specified characteristic peak, the method further comprises: if it is determined that the characteristic peaks of the gamma spectrum data do not include other characteristic peaks in addition to the specified characteristic peak, determining a third nuclide in the target radioactive source by half-life measurement; determining the third nuclide as the nuclide composition of the target radioactive source.

7. The nuclide identification method according to any one of claims 1 to 6, characterized in that, The specified characteristic peak is a positron annihilation peak, and the specified energy peak value is 0.511 Mev.

8. A nuclide identification apparatus, characterized by comprising: The device comprises: a gamma spectrum data acquisition module, configured to acquire gamma spectrum data of a target radioactive source; wherein the characteristic peaks of the gamma spectrum data include a specified characteristic peak, and the specified characteristic peak has a specified energy peak value; a first determination module, configured to determine whether the characteristic peaks of the gamma spectrum data include other characteristic peaks in addition to the specified characteristic peak; a first calculation module, configured to, if yes, determine, according to the gamma spectrum data, a first peak area corresponding to the other characteristic peaks and a second peak area of the specified characteristic peak; each of the other characteristic peaks corresponds to a first nuclide; a second calculation module, configured to determine, according to the first peak area and a peak branching ratio of each of the first nuclides, a total area of the specified characteristic peak contributed by all nuclides of the target radioactive source; a second determination module, configured to determine, according to the second peak area and the total area, whether the target radioactive source includes a second nuclide having only the specified energy peak value; a third calculation module, configured to, if yes, perform half-life measurement on the target radioactive source twice continuously according to a preset time length to obtain first spectrum data and second spectrum data; calculate, based on the first spectrum data and the second spectrum data respectively, areas of the specified characteristic peak contributed by the second nuclide, to obtain a first contribution area and a second contribution area correspondingly; calculate, based on the first contribution area and the second contribution area, a half-life of the second nuclide; and determine, according to the half-life, the second nuclide in the target radioactive source; a nuclide composition determination module, configured to determine a nuclide composition of the target radioactive source according to the first nuclide and the second nuclide; wherein the step of determining, according to the first peak area and a peak branching ratio of each of the first nuclides, a total area of the specified characteristic peak contributed by all nuclides of the target radioactive source comprises: the total area of the specified characteristic peak is calculated by the following formula: S P ； wherein n is the total number of nuclides; S i a is the peak area of the i-th nuclide of the target radioactive source; E i a is the peak branch ratio of the other characteristic peak of the i-th nuclide of the target radioactive source; E i p is the peak branch ratio of the specified characteristic peak of the i-th nuclide of the target radioactive source.

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