Automatic measurement and analysis system based on unmanned gamma spectrum laboratory

Abstract

The invention belongs to the technical field of automatic measurement and analysis of unmanned laboratories, and particularly discloses and provides an automatic measurement and analysis system based on an unmanned gamma spectrum laboratory, which is characterized in that a sample to be measured is sent to a sampling port by a sample preparation worker, and two-dimensional code information attached to the sample is read through an unmanned robot; the method comprises the following steps: constructing a gamma ray energy counting range of a sample, determining an adaptive gamma spectrometer of the sample, autonomously conveying the sample to the adaptive gamma spectrometer, automatically completing detection by a measurement system, autonomously analyzing a sample detection result and uploading a measurement report to a server after detection is finished, and sending the detected sample to a specified position by an unmanned robot; the automatic measurement system of the gamma spectrometer can complete peak-splitting operation automatic analysis of a corresponding overlapped peak shape spectrum region of a gamma spectrum, accurately identify radionuclides in a part of nuclide samples which are difficult to distinguish originally, give an analysis report, and perform peak-shifting identification on identifiable nuclide information in a complete peak shape; according to the method, the accuracy degree of nuclide identification is greatly improved, and the nuclide activity concentration is automatically calculated according to the sample type. And analyzing the risk index of the nuclide activity of the sample to determine the treatment mode of the detected sample.

Description

Technical Field

[0001] The invention belongs to the technical field of automatic measurement and analysis of unmanned laboratories, and relates to an automatic measurement and analysis system based on an unmanned gamma spectrum laboratory. Background Art

[0002] The importance of radioactive material detection in many fields is becoming increasingly prominent, such as nuclear industry safety monitoring, environmental radioactivity assessment, and quality control of radiopharmaceuticals in nuclear medicine diagnosis and treatment. In the process of manually operated γ spectrum measurement, personnel frequently come into contact with radioactive samples, which inevitably increases the risk of radiation exposure and poses a potential threat to the health of workers. In addition, the efficiency of manual operation is relatively low, and it is difficult to meet the growing demand for sample detection. In order to overcome the above problems and realize the efficient, accurate, safe and automated measurement and analysis of γ spectrum of radioactive samples, the present invention proposes an automatic measurement and analysis system based on an unmanned γ spectrum laboratory.

[0003] In the prior art, there are also some related solutions involving automatic measurement and analysis in unmanned laboratories. For example, the Chinese patent publication number CN110780338B discloses a method and system for automatically analyzing total gamma in radioactive samples. The system includes: a running rabbit system for transporting running rabbit bottles, a first mobile module for moving the running rabbit bottles to a temporary storage area, a temporary storage area for temporarily storing the running rabbit bottles, a second mobile module for sampling the samples to a measuring device, two gamma energy spectrum detectors for measuring the samples, and a screening module for screening the measurement data. The running rabbit technology is combined with the total gamma measurement and analysis by sample transfer to realize unattended automatic analysis of samples, which will greatly reduce the labor intensity of the staff and greatly improve work efficiency. The two gamma energy spectrum detectors cover the total gamma and low sections within the measurement range, solving the problem of large total gamma span.

[0004] Although the above scheme solves the problem of automatic measurement in unmanned laboratories, it still has the following limitations: 1. It is impossible to directly extract the pre-processing information during sample preparation, and when measuring γ data, the selectable γ energy spectrum detectors are limited, resulting in a lack of accuracy in the selection of sample detection equipment.

[0005] 2. There is a lack of quality assurance for the gamma spectrum analysis results of automatic measurement and automatic quantitative analysis. The possible ambiguity in the experimental results will lead to deviations in the gamma spectrum detection results. For example, if the overlapping peak areas in the gamma spectrum are not considered for single peak decomposition and identification, the accuracy of the gamma spectrum detection results may be biased, which will lead to a lack of reliability in the detection of the sample nuclide composition information. Summary of the invention

[0006] In view of this, in order to solve the problems raised in the above background technology, an automatic measurement and analysis system based on an unmanned γ spectrum laboratory is proposed.

[0007] The object of the present invention can be achieved by the following technical solution: The present invention provides an automatic measurement and analysis system based on an unmanned γ spectrum laboratory, the system comprising:

[0008] Sample identification module: used to establish equipment parameter sets for different automatic sample-changing high-purity germanium gamma spectrometers, and to scan and retrieve sample QR code information through a humanoid robot. The sample QR code information includes sample source information, pre-treatment information, and pre-detection label information.

[0009] Sample transport module: used to determine the compatible gamma spectrometer of the sample based on the sample QR code information, and to construct a transport path between the sample and the compatible gamma spectrometer, and then transport the sample to the compatible gamma spectrometer through a humanoid robot for subsequent detection operations.

[0010] Automatic measurement and analysis module: used to extract the gamma spectrum and its data set adapted for automatic measurement by the gamma spectrometer. The gamma spectrum data set includes each determined nuclide and its peak parameters, activity, and analyzes the clarity indicators of the detection results.

[0011] Measurement result analysis module: used to analyze the radionuclide activity hazard index of the sample based on the gamma spectrum data set automatically measured by the adapted gamma spectrometer, the clarity index of the test result, and the sample source information in the QR code information.

[0012] Compared with the prior art, the present invention has the following beneficial effects: (1) The present invention uses a two-dimensional code to identify the information of the prepared samples, and places all laboratory gamma spectrometers in an unmanned laboratory. The humanoid robot in the unmanned laboratory identifies the sample information read by the two-dimensional code, constructs the sample gamma ray energy counting range, determines the sample's matching gamma spectrometer, and autonomously transports the sample to the matching gamma spectrometer, which helps to increase the selection diversity and detection accuracy of the sample detection equipment. After the detection, the sample detection results are autonomously analyzed and the detected samples are sent to the designated location. The entire laboratory relies on robots to complete fully automatic measurement and fully automatic analysis related operations, which can eliminate the need for personnel to come into close contact with radioactive samples, reduce the number of personnel entering the operation site, and effectively reduce the risk of radiation exposure to the staff, thereby maximizing the health and safety of the staff, while improving the measurement speed and analysis capabilities, and realizing the standardization of sample measurement.

[0013] (2) The present invention performs a peak deconvolution operation on the corresponding overlapping peak spectral areas of the gamma spectrum automatically measured by the adapted gamma spectrometer, thereby accurately identifying some nuclides that were originally difficult to distinguish, and at the same time performs peak staggered identification on the identifiable nuclide information in the complete peak shape to analyze the clarity index of the test results, which greatly improves the accuracy of nuclide identification and helps to obtain more reliable sample nuclide composition information. BRIEF DESCRIPTION OF THE DRAWINGS

[0014] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the accompanying drawings required for describing the embodiments will be briefly introduced below. Obviously, the accompanying drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other accompanying drawings can be obtained based on these accompanying drawings without paying creative work.

[0015] Figure 1 It is a schematic diagram of the connection of the system modules of the present invention.

[0016] Figure 2 It is a schematic diagram of the implementation process of the sample delivery module of the present invention.

[0017] Figure 3 This is a schematic diagram of the corresponding contents of the sample processing method determined in the present invention. DETAILED DESCRIPTION

[0018] The following will be combined with the drawings in the embodiments of the present invention to clearly and completely describe the technical solutions in the embodiments of the present invention. Obviously, the described embodiments are only part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0019] See also Figure 1 As shown, the present invention provides an automatic measurement and analysis system based on an unmanned γ spectrum laboratory, the system comprising: a sample identification module, a sample conveying module, an automatic measurement and analysis module, a measurement result analysis module, and a sample recovery module.

[0020] The sample identification module is connected to the sample delivery module, the sample delivery module is connected to the automatic measurement and analysis module, the automatic measurement and analysis module is connected to the measurement result analysis module, and the measurement result analysis module is connected to the sample recovery module.

[0021] The sample identification module is used to establish equipment parameter sets for different automatic sample-changing high-purity germanium gamma spectrometers, and to scan and retrieve sample QR code information through a humanoid robot. The sample QR code information includes sample source information, pre-processing information, and pre-detection label information.

[0022] The sample two-dimensional code information is imported by the operator when preparing the sample.

[0023] The sample source information includes sample number, location distance of the sample relative to the radiation point of the radioactive element, sample extraction depth, sample box type, sample net weight or volume and other information.

[0024] The different automatic sample-changing gamma spectrometers include sodium iodide (NaI) scintillation detectors, high purity germanium (HPGe) detectors, sodium iodide (NaI) scintillation detectors, lanthanum bromide (LaBr3) detectors, cerium bromide (CeBr3), cadmium zinc telluride (CdZnTe) detectors, etc.

[0025] The equipment parameter set of the automatic sample-changing gamma spectrometer includes energy resolution, detection efficiency, applicable nuclide range, and measurement accuracy.

[0026] In a preferred embodiment, the method of scanning and retrieving sample QR code information by a humanoid robot specifically includes: sending task information to a robot control module through an information terminal, and the robot control module sends a scanning instruction after receiving the task information, starting a scanning operation, obtaining a sample QR code image, and then decoding and analyzing the QR code image to extract the information contained therein.

[0027] The decoded information is compared and verified with the task information received by the robot control module, and the sample attached to the QR code image is recorded as the test sample. When the decoded information is consistent with the task information received by the robot control module, the subsequent operation on the test sample is continued; when the information is inconsistent, the corresponding abnormal alarm of the test sample is sent to the information terminal through the robot control module.

[0028] The sample conveying module is used to determine the compatible gamma spectrometer of the sample based on the sample QR code information, and to construct a conveying path between the sample and the compatible gamma spectrometer, and then to convey the sample to the compatible gamma spectrometer through a humanoid robot for subsequent detection operations.

[0029] See also Figure 2 As shown, in a preferred embodiment, the determination of the adapted γ spectrometer of the sample includes:

[0030] Tp1. Extract the pre-processing information in the sample QR code information, which includes the preparation time and sample morphology information, and analyze the sample activity fuzzy coefficient υ.

[0031] Tp2. Extract the pre-detection label information in the sample QR code information. The pre-detection label information includes the estimated type set of radionuclides and the activity range. Obtain the γ-ray energy emitted by various radionuclides in the estimated type set of radionuclides from the nuclide decay chart stored in the internal memory of the humanoid robot, and then obtain the maximum and minimum values ​​of the γ-ray energy to form an interval, which is defined as the sample γ-ray energy range [E - , E + ].

[0032] The estimated types of radionuclides include natural radionuclides (uranium series nuclides, thorium series nuclides), artificial radionuclides (nuclear fission products, activation products), medical radionuclides ( 99m Tc, 131 I).

[0033] The activity refers to the number of atomic nuclei of a radionuclide that decays per unit time, and reflects the strength of the decay of the radionuclide.

[0034] Tp3, record the activity range of various radionuclides in the estimated radionuclide category as [A - , A + ], construct the sample gamma-ray energy counting range Then, it is matched with the corresponding energy counting range of each preset energy zone resolution to screen out the energy zone resolution that matches the sample gamma ray energy counting range.

[0035] The resolution of each energy region refers to the expected detection resolution of the detector corresponding to different energy ranges. For example, for the low-energy region of gamma rays with energy below tens of keV, due to its low energy itself, the statistical fluctuation of the detector's detection is relatively large, and a higher energy resolution is usually required to accurately distinguish gamma rays of different energies. Generally, the expected resolution can reach below 1keV or even hundreds of eV to ensure that the gamma ray peaks in the low-energy region can be clearly identified and analyzed to avoid peak overlap and misjudgment.

[0036] For the medium energy region with energy ranging from several hundred keV to several MeV, an energy resolution of about 0.1% to 0.2% can meet the needs of repeated peak analysis. For the high energy region with energy above several MeV, although its energy is higher and the peak broadening is relatively small, due to the increased complexity of the interaction between high-energy gamma rays and detectors, a certain resolution is also required to ensure measurement accuracy.

[0037] Tp4. Select from the various automatic sample-changing gamma spectrometers a gamma spectrometer that can identify all nuclides in the estimated type set of radioactive nuclides and whose gamma-ray energy resolution can cover the resolution of the energy range of the sample gamma-ray energy counting range as the sample-adapted gamma spectrometer.

[0038] In a further preferred embodiment, the analysis of the sample activity fuzzy coefficient includes: extracting the sample particle size difference feature g and the color value difference feature tr from the sample morphology information, analyzing the sample heterogeneity index Wherein g0 and tr0 represent the preset reference particle size difference feature and reference color value difference feature respectively.

[0039] Specifically, for sample morphology, if the prepared sample has an irregular shape or uneven particle size, when placed in a gamma spectrometer for measurement, it will lead to inconsistent absorption and scattering of gamma rays in the sample, thereby affecting the repeatability and accuracy of the measurement results.

[0040] The corresponding method for obtaining the sample particle size difference feature is: identifying all solid particle distribution volumes from the sample two-dimensional code image, comparing them with each other, identifying the average difference volume of the solid particles, and then using it as a numerator to compare with the preset reference difference volume to obtain the sample particle size difference feature.

[0041] The corresponding method for obtaining the color value difference feature is: using image editing software or professional image analysis tools to mark the boundaries of different color value areas in the sample two-dimensional code image, measure their grayscale values, and obtain the average grayscale difference value by comparing the grayscale values ​​of different color value areas. The average grayscale difference value is used as a numerator and compared with a preset reference grayscale difference value to obtain the color value difference feature.

[0042] Extract the preparation time t1 from the pre-processing information of the sample QR code information, compare it with the current detection time, determine the sample storage period T0, and obtain the decay period T of various radionuclides in the estimated radionuclide type set from the nuclide decay chart stored in the internal memory of the humanoid robot. i , infer the sample activity decay index min(T i ) represents the corresponding minimum period of decay of various radioactive nuclides, i represents the number of various radioactive nuclides, i = 1, 2, ..., n.

[0043] Obtain the energy characteristics of various radionuclides in the estimated radionuclide category set from the nuclide decay chart stored in the internal memory of the humanoid robot, including the nuclide range characteristic Y and the penetration ability characteristic Z, and analyze the sample activity fuzzy coefficient Where Y0 and Z0 represent the preset reference values ​​of the nuclide range characteristics and penetration capability characteristics respectively.

[0044] Specifically, different energy characteristics of different radionuclides will affect the accuracy of detection. For example, nuclides with short range have more serious self-absorption in the sample, which may cause the measured activity to be lower than the actual activity; while nuclides with strong penetrating ability are less affected by self-absorption, but there may be problems such as scattering, which will affect the accuracy of activity detection.

[0045] In a further preferred embodiment, the construction of the transport path for the sample and the adapted gamma spectrometer includes: laying electromagnetic induction lines on the floor of the unmanned laboratory to form a specific guide path between the automatic sample changing high-purity germanium gamma spectrometers in the sample preparation area, and then installing an electromagnetic induction sensor on the bottom of the humanoid robot to walk along the specific guide path between the sample and the adapted gamma spectrometer by inducing electromagnetic signals.

[0046] When the humanoid robot reaches the area where the gamma spectrometer is located, the humanoid robot controls the removal of the sample and completes subsequent placement operations.

[0047] The automatic measurement and analysis module is used to extract the gamma spectrum and its data set adapted for automatic measurement by the gamma spectrometer, the gamma spectrum data set including each determined nuclide and its peak parameters, activity, and analyze the clarity index of the detection result.

[0048] In a preferred embodiment, the extraction of the gamma spectrum automatically measured by the gamma spectrometer and its data set includes: obtaining the gamma spectrum automatically measured by the gamma spectrometer, comparing it with the standard gamma spectrum of known radionuclides, matching the peak contours through contour recognition technology, obtaining the types of radionuclides that are obviously present in the gamma spectrum automatically measured by the gamma spectrometer, and locating the multi-peak composite overlapping peak spectral area.

[0049] The multi-peak deconvolution algorithm is used to decompose the overlapping peak spectral area into single peaks, and then the peak parameters of each single peak are obtained. The peak parameters include the peak position and the peak area corresponding to the γ-ray counts. Then, the peak parameters of each single peak obtained by deconvolution are compared with the corresponding peak parameters in the standard γ spectrum of known radioactive nuclides to obtain the types of radionuclides corresponding to each single peak with matching peak parameters.

[0050] The obviously existing radioactive nuclide species and the corresponding radioactive nuclide species of each single peak are integrated into the determined species of each nuclide belonging to the sample, and then the activity of each determined nuclide belonging to the sample is calculated based on the peak parameters to which it belongs. The specific calculation method is as follows: the detection efficiency ε and the measurement time t are derived from the adapted γ spectrometer, and the branching ratio p of each determined nuclide emitting a specified γ ray is obtained. r , calculate the activity of each nuclide in the sample Where N r It indicates that the peak area in the peak parameter of the rth determined nuclide corresponds to the gamma-ray count, r indicates the number of each determined nuclide, r = 1, 2, ..., m.

[0051] Specifically, the peak area corresponding to the gamma-ray count refers to the total number of gamma-rays detected by the detector within the range of a specific peak in the gamma spectrum.

[0052] The branching ratio of each determined nuclide emitting a certain specified gamma ray is a fixed characteristic, which means that when a radioactive nuclide decays, it may decay through a variety of different pathways or modes, and may emit a variety of gamma rays with different energies during the decay process. For a gamma ray of a certain specific energy, its branching ratio is the ratio of the number of times the nuclide decays by emitting this specific energy gamma ray in all decay modes to the total number of decays. For example, a certain radioactive nuclide has three possible decay modes in the decay process, emitting gamma rays with energies of E1, E2, and E3 respectively, among which the number of times the gamma ray decays by emitting gamma rays with energy E1 accounts for 30% of the total number of decays, then the branching ratio of the gamma ray emitted by the nuclide with energy E1 is 30% or 0.3.

[0053] In a further preferred embodiment, the clarity index of the analysis and detection results includes: obtaining the area of ​​the peak spectrum region obtained by deconvolution without decomposition, and identifying its proportion K relative to the total area of ​​the overlapping peak spectrum region.

[0054] The peak position extracted from the peak parameters of each determined nuclide is compared with the fixed position of the corresponding nuclide to identify the peak displacement of each determined nuclide Then analyze the clarity index of the test results in represents the preset reference peak displacement, and e represents the natural constant.

[0055] The present invention performs a peak deconvolution operation on the corresponding overlapping peak spectral areas of the gamma spectrum automatically measured by an adapted gamma spectrometer, thereby accurately identifying some nuclides that were originally difficult to distinguish, and simultaneously performs staggered peak recognition on the identifiable nuclide information in the complete peak shape to analyze the clarity index of the test result, which greatly improves the accuracy of nuclide identification and helps to obtain more reliable sample nuclide composition information.

[0056] The measurement result analysis module is used to analyze the radionuclide activity hazard index of the sample based on the gamma spectrum data set automatically measured by the adaptive gamma spectrometer, the clarity index of the detection result, and the sample source information in the two-dimensional code information.

[0057] In a preferred embodiment, the radionuclide activity hazard index of the analyzed sample includes: a method for obtaining the decay period of various radionuclides based on the estimated type of radionuclides, and similarly obtaining the decay period T of each determined nuclide. rThe sample source information is used to extract the distance L of the sample relative to the radiation point of the radioactive element and the sample extraction depth W, and the risk factors of each determined nuclide to which the sample belongs are analyzed. Where T′ represents the preset reference decay period, L0 and W0 represent the corresponding preset reference values ​​of position distance and sample extraction depth, respectively.

[0058] The radioactive element radiation point may be, for example, a nuclear power plant, and the sample extraction depth may be, for example, the soil cover depth to which the sample belongs.

[0059] The activity A of each determined nuclide in the extracted sample r , analyze the radionuclide activity hazard index of the sample in It indicates the maximum value among the activity hazard levels of each determined nuclide.

[0060] The sample recovery module is used to match the sample hazardous activity limit index, and then determine the sample processing method according to the sample measurement result.

[0061] In a preferred embodiment, the matching of the sample hazardous activity limit index includes: obtaining the specified activity standards of each determined nuclide, comparing them with each other and selecting the minimum value as the sample hazardous activity limit index.

[0062] See also Figure 3 As shown, in a further preferred embodiment, the determination of the sample processing method includes: comparing the sample nuclide activity hazard index with the sample hazard activity limit index to obtain the sample nuclide activity hazard weight φ0 represents the sample hazardous content limit index, and then the sample nuclide activity hazard weight is matched with the preset nuclide activity hazard weight range corresponding to each hazard level to obtain the sample nuclide activity hazard level, and then it is compared with the preset treatment methods corresponding to each nuclide activity hazard level to match the sample nuclide activity hazard weight corresponding treatment method, each hazard level includes high hazard level, medium hazard level, low hazard level, and the treatment methods include deep geological disposal, solidification treatment, and dilution discharge.

[0063] The specific contents of the treatment methods are as follows: when the danger level of the nuclide content in the sample is at a high danger level, the sample is subjected to deep geological disposal. For example, spent fuel and high-level waste liquid produced by nuclear reactors usually require deep geological disposal; when the danger level of the nuclide content in the sample is at a medium danger level, the sample is solidified. Commonly used solidification methods include cement solidification, asphalt solidification, plastic solidification, etc., which fix the radioactive nuclides in a stable solidified body to prevent their diffusion; when the danger level of the nuclide content in the sample is at a low danger level, the sample is diluted and discharged.

[0064] The present invention determines the post-test sample treatment method by analyzing the radionuclide activity hazard index of the sample, which can avoid the random discharge or leakage of radioactive substances into environmental media such as soil, water, and air, and select appropriate disposal methods for samples of different hazard levels, which helps to prevent the sample body from causing long-term and irreparable pollution hazards to the ecological environment.

[0065] The present invention uses a two-dimensional code to identify the information of the prepared samples, and places all laboratory gamma spectrometers in an unmanned laboratory. The humanoid robot in the unmanned laboratory identifies the sample information read by the two-dimensional code, constructs the sample gamma ray energy counting range, determines the sample's matching gamma spectrometer, and autonomously transports the sample to the matching gamma spectrometer, which helps to increase the selection diversity and detection accuracy of the sample detection equipment, and then autonomously analyzes the sample detection results after the detection, and sends the detected samples to the designated location. The entire laboratory relies on robots to complete fully automatic measurement and fully automatic analysis related operations, which can eliminate the need for personnel to come into close contact with radioactive samples, reduce the number of personnel entering the operation site, and effectively reduce the risk of radiation exposure to the staff, thereby maximizing the health and safety of the staff, while improving the measurement speed and analysis capabilities, and realizing the standardization of sample measurement.

[0066] The above contents are merely examples and explanations of the concept of the present invention. Those skilled in the art may make various modifications or additions to the specific embodiments described or replace them in a similar manner. As long as they do not deviate from the concept of the invention or exceed the scope defined by the present invention, they shall all fall within the protection scope of the present invention.

Claims

1. An automatic measurement and analysis system based on an unmanned γ spectrum laboratory, characterized in that: The system includes: Sample identification module: used to establish equipment parameter sets for different automatic sample-changing gamma spectrometers, and to scan and retrieve sample QR code information through a humanoid robot. The sample QR code information includes sample source information, pre-treatment information, and pre-detection label information; Sample delivery module: used to determine the compatible γ spectrometer of the sample based on the sample QR code information, and to construct a delivery path between the sample and the compatible γ spectrometer, and then to deliver the sample to the compatible γ spectrometer through a humanoid robot for subsequent detection operations; Automatic measurement and analysis module: used to extract the gamma spectrum and its data set adapted for automatic measurement by the gamma spectrometer. The gamma spectrum data set includes each determined nuclide and its peak parameters and activity, and analyzes the clarity index of the test results; Measurement result analysis module: used to analyze the radionuclide activity hazard index of the sample based on the gamma spectrum data set automatically measured by the adapted gamma spectrometer, the clarity index of the test result, and the sample source information in the QR code information; Sample recovery module: used to match the sample's hazardous activity limit index, and then determine the sample processing method based on the sample's measurement results.

2. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 1, characterized in that: The method of scanning and retrieving the sample QR code information by the humanoid robot specifically includes: sending task information to the robot control module through the information terminal, and the robot control module sends a scanning instruction after receiving the task information, starts the scanning operation, obtains the sample QR code image, and then decodes and analyzes the QR code image to extract the information contained therein; The decoded information is compared and verified with the task information received by the robot control module, and the sample attached to the QR code image is recorded as the test sample. When the decoded information is consistent with the task information received by the robot control module, the subsequent operation on the test sample is continued; when the information is inconsistent, the corresponding abnormal alarm of the test sample is sent to the information terminal through the robot control module.

3. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 1, characterized in that: The determination of the suitable gamma spectrometer for the sample comprises: Tp1, extract the pre-processing information in the sample QR code information, the pre-processing information includes preparation time, sample morphology information, and analyze the sample activity fuzzy coefficient υ; Tp2. Extract the pre-detection label information in the sample QR code information. The pre-detection label information includes the estimated type set of radionuclides and the activity range. Obtain the γ-ray energy emitted by various radionuclides in the estimated type set of radionuclides, and then obtain the maximum and minimum values ​​of the γ-ray energy to form an interval, which is defined as the sample γ-ray energy range [E - , E + ]; Tp3, record the activity range of various radionuclides in the estimated radionuclide category as [A - , A + ], construct the sample gamma-ray energy counting range Then, it is matched with the corresponding energy counting range of each preset energy zone resolution, and the energy zone resolution matching the energy counting range of the sample gamma ray is screened out; Tp4. Select from the various automatic sample-changing gamma spectrometers a gamma spectrometer that can identify all nuclides in the estimated type set of radioactive nuclides and whose gamma-ray energy resolution can cover the resolution of the energy range of the sample gamma-ray energy counting range as the sample-adapted gamma spectrometer.

4. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 3, characterized in that: The analysis of sample activity fuzzy coefficient includes: extracting sample size difference characteristics and color difference characteristics from sample morphology information, analyzing sample heterogeneity index Extract the preparation time t1 from the pre-processing information of the sample QR code information, compare it with the current detection time, determine the sample storage period T0, and obtain the decay period T of various radionuclides in the estimated radionuclide type set i , infer the sample activity decay index min(T i ) represents the corresponding minimum period of decay of various radioactive nuclides, i represents the number of various radioactive nuclides, i = 1, 2, ..., n; Obtain the energy characteristics of various radionuclides in the estimated radionuclide category set, including the nuclide range characteristic Y, the penetration ability characteristic Z, and analyze the sample activity fuzzy coefficient Where Y0 and Z0 represent the preset reference values ​​of the nuclide range characteristics and penetration capability characteristics respectively.

5. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 1, characterized in that: The construction of the conveying path of the sample and the matching gamma spectrometer includes: laying electromagnetic induction lines on the floor of the unmanned laboratory to form a specific guide path between the automatic sample changing gamma spectrometers in the sample preparation area, and then installing an electromagnetic induction sensor on the bottom of the humanoid robot to walk along the specific guide path of the sample and the matching gamma spectrometer by sensing electromagnetic signals; When the humanoid robot reaches the area where the gamma spectrometer is located, the humanoid robot controls the removal of the sample and completes subsequent placement operations.

6. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 1, characterized in that: The method of extracting the gamma spectrum automatically measured by the gamma spectrometer and its data set comprises: obtaining the gamma spectrum automatically measured by the gamma spectrometer, comparing it with the standard gamma spectrum of known radionuclides, matching the peak profiles by the profile recognition technology, obtaining the types of radionuclides obviously existing in the gamma spectrum automatically measured by the gamma spectrometer, and locating the multi-peak composite overlapping peak spectrum area; A multi-peak deconvolution algorithm is used to decompose overlapping peak spectral regions into single peaks, and then obtain the peak parameters of each single peak. The peak parameters include the peak position and the corresponding gamma-ray counts of the peak area. Then, the peak parameters of each single peak obtained by deconvolution are compared with the corresponding peak parameters in the standard gamma spectrum of known radioactive nuclides to obtain the types of radionuclides corresponding to each single peak with matching peak parameters. The types of radionuclides that are obviously present and the types of radionuclides corresponding to each single peak are integrated into the determined types of each nuclide belonging to the sample, and then based on the peak parameters to which they belong, the activity of each determined nuclide belonging to the sample is calculated.

7. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 5, characterized in that: The clarity index of the analysis and detection results includes: obtaining the peak spectral area obtained by deconvolution without decomposition, and identifying its proportion K relative to the total area of ​​the overlapping peak spectral area; The peak position extracted from the peak parameters of each determined nuclide is compared with the fixed position of the corresponding nuclide to identify the peak displacement Δl of each determined nuclide r , and then analyze the clarity index of the test results Wherein Δl′ represents the preset reference peak displacement, r represents the number of each determined nuclide, r=1, 2,…, m, and e represents a natural constant.

8. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 7, characterized in that: The analysis of the radionuclide activity hazard index of the sample includes: obtaining the decay period of each determined nuclide, extracting the location distance of the sample relative to the radiation point of the radioactive element and the sample extraction depth from the sample source information, and analyzing the hazard factor β of each determined nuclide of the sample. r ; The activity A of each determined nuclide in the extracted sample r , analyze the radionuclide activity hazard index of the sample in It indicates the maximum value among the activity hazard levels of each determined nuclide.

9. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 1, characterized in that: The matching of the sample hazardous activity limit index includes: obtaining the specified activity standards of each determined nuclide, comparing them with each other and selecting the minimum value as the sample hazardous activity limit index.

10. The automatic measurement and analysis system based on an unmanned γ spectrum laboratory according to claim 1, characterized in that: The method of determining the sample processing method includes: comparing the radionuclide activity hazard index of the sample with the sample hazardous activity limit index to obtain the sample radionuclide activity hazard weight, and determining the sample radionuclide activity hazard level based on this, and then comparing it with the corresponding preset processing methods of each radionuclide activity hazard level to match the corresponding processing method of the sample radionuclide activity hazard weight, each hazard level includes a high hazard level, a medium hazard level, and a low hazard level, and the processing methods include deep geological disposal, solidification treatment, and dilution discharge.

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