Radioactive steel ingot activity rapid nondestructive measurement device and measurement method

Abstract

The invention discloses a rapid nondestructive measurement device and method for the activity of a radioactive steel ingot. The rapid nondestructive measurement device comprises a control module, a transmission module, a mass measurement module, a spectrum measurement module and an analysis and calculation module, the control module is used for controlling the cooperative operation of the transmission module, the quality measurement module and the spectrum measurement module to realize the automation of the measurement process; the transmission module is used for driving the radioactive steel ingot to be measured to reach a preset mass measurement position and an energy spectrum measurement position; the mass measurement module is used for acquiring mass data of the radioactive steel ingot to be measured; the spectrum measurement module is used for acquiring an energy spectrum emitted by the radioactive steel ingot to be measured under a shielding condition; monte Carlo calculation software is arranged in the analysis and calculation module, and the analysis and calculation module is used for calculating full-energy-peak simulation detection efficiency based on passive efficiency scales and outputting a nuclide activity analysis result of the radioactive steel ingot to be detected in combination with the energy spectrum and quality data.

Description

Technical Field

[0001] This invention relates to the field of nuclear radioactive waste treatment and disposal, specifically to a rapid and non-destructive measurement device and method for the activity of radioactive steel ingots. Background Technology

[0002] The operation, maintenance, and decommissioning of nuclear facilities generate a large amount of radioactive metal waste. In the field of radioactive waste treatment and disposal, smelting technology is commonly used to cast this waste into radioactive steel ingots. This reduces the volume of waste, facilitating subsequent final disposal, and allows for further rolling to create waste containers for reuse. Accurately measuring the radioactivity of these ingots is a crucial step in determining their radioactivity levels and classifying them for appropriate disposal, possessing significant economic value and environmental safety implications.

[0003] Currently, methods for measuring nuclide activity in solid waste are divided into destructive and non-destructive methods. For activity measurements of large-volume, high-density objects like radioactive steel ingots, the industry lacks mature and effective non-destructive measurement solutions, and destructive laboratory analytical methods are commonly used. This method requires cutting or grinding representative samples from the steel ingot, then sending the samples to a specialized radiochemistry laboratory for a series of processing and analytical steps. This sampling laboratory analytical method is complex, time-consuming, and costly. Furthermore, due to the potential for non-uniform distribution of nuclides within the steel ingot, local sampling results may not fully represent the overall activity of the entire several-ton ingot, posing a risk of significant measurement uncertainty.

[0004] In the field of radioactive waste treatment and disposal, non-destructive measurement (NDT) techniques, especially gamma-ray spectroscopy-based measurement systems, have been widely used for activity measurement of 200-liter standard waste containers. These systems are typically equipped with shielding, mechanical conveying devices, and fixed high-purity germanium detector arrays. While NDT devices and technologies are primarily used for activity measurement of standard waste containers, there are currently no NDT devices specifically designed for the unique measurement target of radioactive steel ingots.

[0005] When dealing with non-standard, large-volume samples, existing non-destructive measurement techniques typically employ the active efficiency calibration method. This involves using a calibration source with known activity that is similar in shape and matrix to the sample to be tested for experimental calibration. However, the active efficiency calibration method requires the fabrication of a simulated calibration source that is completely identical to a real radioactive steel ingot in terms of size, density, and elemental composition, which is costly and complex. Summary of the Invention

[0006] To achieve the above and other related objectives, this invention discloses a rapid and non-destructive measurement device for the activity of radioactive steel ingots, comprising a control module, a transmission module, and a mass measurement module. Spectrum measurement module and analysis and calculation module: The control module is used to control the transmission module, the mass measurement module, and the... The coordinated operation of the spectral measurement modules enables the automation of the measurement process; The transmission module is used to drive the radioactive steel ingot to be tested to a preset mass measurement position. Location of energy spectrum measurement; The mass measurement module is used to acquire the mass data of the radioactive steel ingot to be tested. The The spectral measurement module is used to collect the emissions emitted by the radioactive steel ingot under shielding conditions. Energy spectrum; The analysis and calculation module incorporates Monte Carlo calculation software for calculating the full-energy peak simulation detection efficiency based on a passive efficiency scale. And in conjunction with the above Energy spectroscopy and mass data Output the nuclide activity analysis results of the radioactive steel ingot to be tested.

[0007] Preferably, the transmission module includes a motor, a driving roller, a driven roller, a conveyor belt, and a first support frame. The motor is linked with the driving roller to drive the conveyor belt to move, thereby causing the radioactive steel ingot to be tested to sequentially reach the mass measurement position and the... Location for energy spectrum measurement.

[0008] Preferably, the The spectral measurement module includes a high-purity germanium detector, a shield, and a multichannel analyzer; the shield has an opening facing the radioactive steel ingot to be measured to suppress ambient background radiation; the multichannel analyzer is connected to the high-purity germanium detector to achieve... Acquisition and storage of energy spectrum signals.

[0009] Preferably, the mass measurement module includes a weighing sensor for collecting mass data when the radioactive steel ingot to be tested reaches the mass measurement position. And send it to the analysis and calculation module.

[0010] Secondly, this invention discloses a rapid and non-destructive method for measuring the activity of radioactive steel ingots, applied to the aforementioned device, comprising: Crystal size characterization of high-purity germanium detectors was performed, and an efficiency calculation model for high-purity germanium detectors was established and verified. A non-radioactive steel ingot sample with the same shape, density, and geometric dimensions as the radioactive steel ingot to be tested was placed directly in front of the high-purity germanium detector, and background energy spectrum was collected. The transmission module moves the radioactive steel ingot to be tested to the same fixed geometric measurement position as the non-radioactive steel ingot sample, and collects data from the radioactive steel ingot. Energy spectrum; The parameters required to obtain the passive efficiency calibration include at least the geometrical relationship between the radioactive steel ingot to be tested and the high-purity germanium detector, the geometric dimensions and material parameters of the radioactive steel ingot to be tested, and the mass of the radioactive steel ingot to be tested. The density of the radioactive steel ingot to be tested was calculated based on this. ; Based on the efficiency calculation model of high-purity germanium detectors and the parameters required for passive efficiency calibration, a geometric model including a high-purity germanium detector, a shield, and a steel ingot was established. Monte Carlo simulation was used to obtain different energies. Corresponding full-energy peak simulation detection efficiency ; Based on the radioactive steel ingot to be tested Energy spectrum and background energy spectrum for extracting nuclides of interest In characteristic energy The net peak area at the location is then subtracted from the background energy spectrum, combined with the aforementioned... With steel ingot quality Calculate the activity concentration of nuclides With total activity .

[0011] Preferably, the crystal size characterization of the high-purity germanium detector and the establishment and verification of the high-purity germanium detector efficiency calculation model include: A preset point source was placed at a preset distance directly in front of a high-purity germanium detector for gamma-ray spectrum measurement. The measured detection efficiency of the full-energy peak of gamma rays at each energy level was calculated. Specifically, for energies of [energy value missing], [efficiency details missing]. of X-rays, measured detection efficiency of the full-energy peak satisfy: in, For the preset point source in energy The net peak area of ​​the all-energy peak at that location. To preset the activity of the point source, For the preset point source in energy Branch ratio at point, Preset point source measurement time; A Monte Carlo simulation model was established to calculate the efficiency of a high-purity germanium detector, and the full-energy peak simulated detection efficiency of gamma rays at various energies was calculated. ; By adjusting the parameters of the high-purity germanium detector crystal in the high-purity germanium detector efficiency calculation model, the efficiency of gamma rays at each energy level is improved. and The relative deviation is less than 2%, thus obtaining a verified high-purity germanium detector efficiency calculation model.

[0012] Preferred nuclides In energy Net count rate at the location With activity concentration satisfy: in, The radioactive steel ingot to be tested Nuclides in energy spectrum In energy The net peak area of ​​the all-energy peak at that location. Nuclide in the background energy spectrum In energy The net peak area of ​​the all-energy peak at that location. The radioactive steel ingot to be tested Energy spectroscopy measurement time, The baseline measurement time, nuclide In energy Branch ratio at point, For the quality of steel ingots, nuclide activity concentration, nuclide Total activity.

[0013] Thirdly, the present invention discloses a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the method described thereon.

[0014] By adopting the above technical solution, rapid and accurate measurement without a physical calibration source is achieved: using a precisely characterized detector model and Monte Carlo simulation, passive efficiency calibration can be performed directly, completely avoiding the high cost and process complexity of manufacturing a calibration source that is completely identical to the real steel ingot. It possesses high-precision and wide-range measurement capabilities: through precise geometric modeling, background subtraction, and efficiency calculation, this invention can accurately analyze the activity concentration of multiple γ-ray nuclides in steel ingots, with measurement uncertainty controlled at a low level. Comparison of the measurement results of this invention with the analysis results of a prepared Co-60 standard sample shows a relative deviation of <10%. Theoretically, any nuclide emitting detectable γ-rays can be quantitatively analyzed using this device, with a wide activity measurement range. An integrated and automated field measurement system is formed: this invention integrates transmission, mass measurement, γ-ray spectrum acquisition, and passive efficiency calibration analysis into one unit, automating the measurement process through a control module. This eliminates the reliance on specialized radiochemistry laboratories, enabling direct deployment at nuclear facility sites. It allows for rapid, non-destructive measurement of radioactive steel ingots in a "one-stop" manner, significantly improving measurement efficiency and providing timely and reliable data support for waste classification, disposal, and resource utilization decisions. In summary, this invention effectively fills the technological gap in dedicated non-destructive measurement devices for radioactive steel ingots. With its non-destructive nature, high efficiency, high precision, and excellent field applicability, it provides a powerful technical means for radioactive waste management during the operation and decommissioning of nuclear facilities. Attached Figure Description

[0015] The above and other features, advantages, and aspects of the embodiments of this disclosure will become more apparent from the accompanying drawings and the following detailed description. The drawings are provided for a better understanding of the invention and are not intended to limit the scope of this disclosure. In the drawings, the same or similar reference numerals denote the same or similar elements, wherein: Figure 1 This is an overall schematic diagram of an embodiment of the present invention; Figure 2 This is a schematic diagram of the detector probe and shielding body according to an embodiment of the present invention; Figure 3 This is a schematic diagram of the detection field of view in an embodiment of the present invention.

[0016] Reference numerals: 1. Transmission module; 11. Conveyor belt; 12. Driving roller; 13. Driven roller; 14. Motor; 15. First support frame; 2. Mass measurement module; 21. Weighing sensor; 3. Gamma spectrum measurement module; 31. Shielding body; 32. High-purity germanium detector; 33. Multichannel analyzer; 34. Support frame; 321. Probe; 322. Cold finger; 323. Liquid nitrogen Dewar jar; 324. Foot pad; 325. Connecting wire; 4. Radioactive steel ingot to be tested. Detailed Implementation

[0017] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0018] Reference Figure 1 This invention provides a rapid and non-destructive measurement device for the activity of radioactive steel ingots, comprising a control module, a transmission module 1, a mass measurement module 2, a gamma spectrum measurement module 3, and an analysis and calculation module. The control module is used to control the coordinated operation of the transmission module 1, the mass measurement module 2 and the gamma spectrum measurement module 3 to automate the measurement process. The transmission module 1 is used to drive the radioactive steel ingot 4 to be tested to reach the preset mass measurement position and γ energy spectrum measurement position. The mass measurement module 2 is used to acquire the mass data m of the radioactive steel ingot 4 to be tested; The gamma spectrum measurement module 3 is used to collect the gamma energy spectrum emitted by the radioactive steel ingot 4 under shielding conditions; The analysis and calculation module incorporates Monte Carlo calculation software for calculating the full-energy peak simulation detection efficiency based on a passive efficiency scale. The results of the nuclide activity analysis of the radioactive steel ingot 4 to be tested are output by combining the gamma energy spectrum and mass data m.

[0019] Preferably, the transmission module 1 consists of a motor 14, a drive roller 12, a driven roller 13, a conveyor belt 11, and a first support frame 15, responsible for moving the radioactive steel ingot 4 to be tested. The first support frame 15 is welded from high-strength steel and serves as the core load-bearing foundation, ensuring the stability of the overall structure. All components are installed based on the first support frame 15. The drive roller 12 is directly linked to the motor 14 via a coupling and is installed at one end of the first support frame 15; the driven roller 13 is correspondingly installed at the other end of the first support frame 15 and in an auxiliary position in the middle, used to support and guide the conveyor belt 11. The drive roller 12 and the driven roller 13 are made of stainless steel, with a diameter of approximately 100 mm, and the surface is covered with anti-slip rubber to enhance friction. The conveyor belt 11 is a conveyor belt made of steel wire rope core covered with rubber, the width of which is adapted to the size of the radioactive steel ingot 4 to be tested, typically 500-1000 mm, and is driven by the motor 14 to move the radioactive steel ingot 4 to be tested at a constant speed, for example, 0.1 m / s.

[0020] The mass measurement module 2 mainly includes a load cell 21, which is mounted on the first support frame 15 of the transmission module 1, for example, integrated below or to the side of the conveyor belt 11. The load cell 21 is a high-precision strain gauge sensor with a measuring range of 0-10 tons. When the radioactive steel ingot 4 to be measured moves to the mass measurement position, the load cell 21 automatically collects the mass data and transmits it to the analysis and calculation module via a signal line. To reduce vibration interference, damping pads can be installed around the load cell 21.

[0021] Reference Figure 2 The gamma-ray spectrum measurement module 3 consists of a high-purity germanium detector 32, a shield 31, a second support frame 34, and a multichannel analyzer 33, and is used to collect gamma-ray energy spectra. The shield 31 is a hollow cylinder with a density of 11.34 g / cm³. 3 The shield is made of pure lead, with a thickness of 50 mm, to effectively shield against ambient background radiation. The central hollow cylinder has a diameter of 150 mm. The shield 31 is placed on a second support frame 34. The interior of the shield 31 is lined with a 1-2 mm thick layer of copper or cadmium to reduce interference from lead's characteristic X-rays. The high-purity germanium detector 32 is a P-type HPGe high-purity germanium detector with a relative detection efficiency of 10%-20%. Its detailed structure includes a probe 321 (containing a high-purity germanium crystal), a cold finger 322, a liquid nitrogen Dewar flask 323, and foot pads 324. The liquid nitrogen Dewar flask 323 needs to be periodically filled with liquid nitrogen to maintain the high-purity germanium detector 32 at low temperatures. The high-purity germanium detector 32 is fixed inside the shield 31 by the foot pads 324, with the detection end facing the measurement direction. The measurement distance between the detector and the radioactive steel ingot 4 to be measured is fixed; in this embodiment, it is preferably 500 mm, while ensuring that the detection field of view completely covers the radioactive steel ingot 4 to be measured. The multichannel analyzer 33 is placed on the operating table outside the shield 31 and is connected to the signal output terminal of the high-purity germanium detector 32 via a connecting cable 325. The multichannel analyzer 33 uses 64k channels to realize the conversion, analysis, and storage of gamma spectrum signals. Measurement parameters (such as gain and forming time) are set via software. The second support frame 34 is made of steel and is height adjustable to ensure that the high-purity germanium detector 32 is aligned with the center of the radioactive steel ingot 4 to be tested.

[0022] The analysis and calculation module is a computer placed on the operating table and connected to the multichannel analyzer 33 via USB. The computer is also connected to the control and transmission module 1 and the mass measurement module 2. It performs the following functions: reads the γ-ray spectrum data collected by the multichannel analyzer 33 and performs spectral analysis (such as peak area calculation and background subtraction); controls the operation of the transmission module 1 and the mass measurement module 2; incorporates Monte Carlo simulation software for passive efficiency calibration calculation; and finally outputs the activity concentration and total activity of each γ-nuclide in the steel ingot.

[0023] Secondly, this invention discloses a rapid and non-destructive method for measuring the activity of radioactive steel ingots, applied to the aforementioned device, comprising: The crystal size of the high-purity germanium detector 32 was characterized, and the efficiency calculation model of the high-purity germanium detector 32 was established and verified. A non-radioactive steel ingot sample with the same shape, density, and geometric dimensions as the radioactive steel ingot 4 to be tested was placed directly in front of the high-purity germanium detector 32, and background energy spectrum was collected. The transmission module 1 is used to move the radioactive steel ingot 4 to the same fixed geometric measurement position as the non-radioactive steel ingot sample, and the γ energy spectrum of the radioactive steel ingot 4 is collected. The parameters required to obtain the passive efficiency scale include at least the geometric positional relationship between the radioactive steel ingot 4 to be tested and the high-purity germanium detector 32, the geometric dimensions and material parameters of the radioactive steel ingot 4 to be tested, the mass m of the radioactive steel ingot 4 to be tested, and the density ρ of the radioactive steel ingot 4 to be tested based on these parameters. Based on the efficiency calculation model of the high-purity germanium detector 32 and the parameters required for passive efficiency calibration, a geometric model including the high-purity germanium detector 32, the shield 31, and the radioactive steel ingot 4 to be tested was established. Monte Carlo simulation was used to obtain the simulated detection efficiency of the full-energy peak corresponding to different energies E. ; Based on the radioactive steel ingot to be tested Energy spectrum and background energy spectrum for extracting nuclides of interest In characteristic energy The net peak area at the location is then subtracted from the background energy spectrum, combined with the aforementioned... With steel ingot quality Calculate the activity concentration of nuclides With total activity .

[0024] Preferably, the crystal size characterization of the high-purity germanium detector and the establishment and verification of the high-purity germanium detector efficiency calculation model include: A preset point source was placed at a preset distance directly in front of a high-purity germanium detector for gamma-ray spectrum measurement. The measured detection efficiency of the full-energy peak of gamma rays at each energy level was calculated. Specifically, for energies of [energy value missing], [efficiency details missing]. of X-rays, measured detection efficiency of the full-energy peak satisfy: in, For the preset point source in energy The net peak area of ​​the all-energy peak at that location. To preset the activity of the point source, For the preset point source in energy Branch ratio at point, Preset point source measurement time; A Monte Carlo simulation model was established to calculate the efficiency of a high-purity germanium detector, and the full-energy peak simulated detection efficiency of gamma rays at various energies was calculated. ; By adjusting the parameters of the high-purity germanium detector crystal in the high-purity germanium detector efficiency calculation model, the efficiency of gamma rays at each energy level is improved. and The relative deviation is less than 2%, thus obtaining a verified high-purity germanium detector efficiency calculation model.

[0025] As described above, the preset point source in the embodiments of the present invention uses a standard point source (such as Co-60, Cs-137, Am-241, Eu-152), whose activity... It is known that a preset point source is placed at a fixed distance directly in front of the detector axis, preferably 10 cm in this embodiment of the invention. The γ energy spectrum is measured for a sufficiently long time to ensure that the net peak area of ​​the full energy peak is >10000 and that the statistical error of the net peak area is <1%.

[0026] Calculate the measured detection efficiency for each energy gamma ray. ; A geometric model was built using Monte Carlo simulation software, and calculations were performed under the same geometric conditions. By adjusting parameters such as the length, diameter, and dead layer thickness of the detector crystal in the geometric model, the amount of gamma rays at each energy level can be adjusted. and The relative deviation is less than 2%, thus obtaining a verified high-purity germanium detector efficiency calculation model.

[0027] Preferably, the background energy spectrum is collected including: Reference Figure 3 A non-radioactive steel ingot sample is placed directly in front of the detector. The detection range of probe 321 needs to cover the entire steel ingot, and its shape, density, and geometric dimensions must be consistent with the radioactive steel ingot 4 to be tested. In this embodiment of the invention, it is preferably cylindrical, with a diameter of 500 mm and a height of 300 mm. Ensure that there are no other radioactive sources at the measurement site and turn off any equipment that may interfere. Start the gamma spectrum measurement module 3 to collect the background energy spectrum. The background measurement time is... This is typically for several hours to ensure good statistical results.

[0028] Preferably, the parameters required to obtain the passive efficiency scale include: Geometric parameters: Record the precise positional relationship between the radioactive steel ingot 4 and the high-purity germanium detector 32, including distance and relative position. A laser rangefinder is used to ensure accuracy (±5 mm).

[0029] 4. Dimensions and Material of the Radioactive Steel Ingot to be Tested: The geometric dimensions (such as diameter and height) of the radioactive steel ingot to be tested are obtained through mold drawings or manual measurement. Material parameters are determined through the ingot's source information.

[0030] Mass and density: Obtain the mass m (g) of the radioactive steel ingot 4 to be tested from the mass measurement module 2, and calculate the density ρ (g / cm³) based on the geometric dimensions. 3 For example, for a cylindrical steel ingot, ρ = m / (π × (diameter / 2)). 2 × Height).

[0031] Preferably, based on the efficiency calculation model of the high-purity germanium detector 3 and the parameters required for passive efficiency calibration, a geometric model is established including the high-purity germanium detector 3, the shield 31, and the radioactive steel ingot 4 to be tested. Monte Carlo simulation is used to obtain different energies. Corresponding full-energy peak simulation detection efficiency include: Using Monte Carlo simulation software, the efficiency calculation model of the high-purity germanium detector is imported to establish a geometric model including the high-purity germanium detector 32, the shield 31, and the radioactive steel ingot 4 to be tested. The parameters of the passive efficiency scale also need to be input.

[0032] Set simulation parameters: number of simulated particles ≥ 10 7 The energy is set to the full-energy peak energy obtained from gamma spectroscopy measurements, and different energies are output. Corresponding full-energy peak simulation detection efficiency ; To improve efficiency, this embodiment of the invention simulates common steel ingot specifications and common nuclide gamma-ray energies in advance to establish an efficiency database, which can be directly accessed during measurement.

[0033] Preferred nuclides In energy Net count rate at the location With activity concentration satisfy: in, The radioactive steel ingot to be tested Nuclides in energy spectrum In energy The net peak area of ​​the all-energy peak at that location. Nuclide in the background energy spectrum In energy The net peak area of ​​the all-energy peak at that location. The radioactive steel ingot to be tested Energy spectroscopy measurement time, The baseline measurement time, nuclide In energy Branch ratio at point, For the quality of steel ingots, nuclide activity concentration, nuclide Total activity.

[0034] In this embodiment of the invention, the experimental verification results based on the above method are shown in Table 1: Table 1 Experimental verification results

[0035] Thirdly, the present invention discloses a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the method described thereon.

[0036] It will be understood by those skilled in the art that, unless otherwise defined, all terms used herein (including technical and scientific terms) have the same meaning as commonly understood by one of ordinary skill in the art to which this invention pertains. It should also be understood that terms such as those defined in general dictionaries should be understood to have the meaning consistent with their meaning in the context of the prior art, and should not be interpreted in an idealized or overly formal sense unless specifically defined.

[0037] For the sake of simplicity, the method embodiments are described as a series of actions. However, those skilled in the art should understand that the embodiments of the present invention are not limited to the described order of actions, because according to the embodiments of the present invention, some steps can be performed in other orders or simultaneously. Furthermore, those skilled in the art should also understand that the embodiments described in the specification are preferred embodiments, and the actions involved are not necessarily essential to the embodiments of the present invention.

[0038] As can be seen from the above description of the embodiments, those skilled in the art can clearly understand that this application can be implemented by means of software plus necessary general-purpose hardware platforms. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, can be embodied in the form of a software product. This computer software product can be stored in a storage medium, such as ROM / RAM, magnetic disk, optical disk, etc., and includes several instructions to cause a computer device (which may be a personal computer, server, or network device, etc.) to execute the methods described in various embodiments or some parts of the embodiments of this application.

[0039] Finally, it should be noted that the above embodiments are only used to illustrate the technical solutions of the present invention, and not to limit them; although the present invention has been described in detail with reference to the foregoing embodiments, those skilled in the art should understand that modifications can still be made to the technical solutions described in the foregoing embodiments, or equivalent substitutions can be made to some or all of the technical features; and these modifications or substitutions do not cause the essence of the corresponding technical solutions to deviate from the scope of the technical solutions of the embodiments of the present invention.

Claims

1. A rapid and non-destructive measurement device for the activity of radioactive steel ingots, characterized in that, Includes control module, transmission module, quality measurement module, Spectrum measurement module and analysis and calculation module: The control module is used to control the transmission module, the mass measurement module, and the... The coordinated operation of the spectral measurement modules enables the automation of the measurement process; The transmission module is used to drive the radioactive steel ingot to be tested to a preset mass measurement position. Location of energy spectrum measurement; The mass measurement module is used to acquire the mass data of the radioactive steel ingot to be tested. The The spectral measurement module is used to collect the emissions emitted by the radioactive steel ingot under shielding conditions. Energy spectrum; The analysis and calculation module incorporates Monte Carlo calculation software for calculating the full-energy peak simulation detection efficiency based on a passive efficiency scale. And in conjunction with the above Energy spectroscopy and mass data Output the nuclide activity analysis results of the radioactive steel ingot to be tested.

2. The apparatus according to claim 1, characterized in that, The transmission module includes a motor, a driving roller, a driven roller, a conveyor belt, and a first support frame. The motor is linked with the driving roller to drive the conveyor belt to move, thereby causing the radioactive steel ingot to be tested to sequentially reach the mass measurement position and the... Location for energy spectrum measurement.

3. The apparatus according to claim 1, characterized in that, The The spectral measurement module includes a high-purity germanium detector, a shield, and a multichannel analyzer; the shield has an opening facing the radioactive steel ingot to be measured to suppress ambient background radiation; the multichannel analyzer is connected to the high-purity germanium detector to achieve... Acquisition and storage of energy spectrum signals.

4. The apparatus according to claim 1, characterized in that, The mass measurement module includes a weighing sensor for collecting mass data when the radioactive steel ingot to be tested reaches the mass measurement position. And send it to the analysis and calculation module.

5. A rapid and non-destructive method for measuring the activity of radioactive steel ingots, characterized in that, Applied to the apparatus according to any one of claims 1 to 4, comprising: Crystal size characterization of high-purity germanium detectors was performed, and an efficiency calculation model for high-purity germanium detectors was established and verified. A non-radioactive steel ingot sample with the same shape, density, and geometric dimensions as the radioactive steel ingot to be tested was placed directly in front of the high-purity germanium detector, and background energy spectrum was collected. The transmission module moves the radioactive steel ingot to be tested to the same fixed geometric measurement position as the non-radioactive steel ingot sample, and collects data from the radioactive steel ingot. Energy spectrum; The parameters required to obtain the passive efficiency calibration include at least the geometrical relationship between the radioactive steel ingot to be tested and the high-purity germanium detector, the geometric dimensions and material parameters of the radioactive steel ingot to be tested, and the mass of the radioactive steel ingot to be tested. The density of the radioactive steel ingot to be tested was calculated based on this. ; Based on the efficiency calculation model of high-purity germanium detectors and the parameters required for passive efficiency calibration, a geometric model including a high-purity germanium detector, a shield, and a steel ingot was established. Monte Carlo simulation was used to obtain different energies. Corresponding full-energy peak simulation detection efficiency ; Based on the radioactive steel ingot to be tested Energy spectrum and background energy spectrum for extracting nuclides of interest In characteristic energy The net peak area at the location is then subtracted from the background energy spectrum, combined with the aforementioned... With steel ingot quality Calculate the activity concentration of nuclides With total activity .

6. The method according to claim 5, characterized in that, The crystal size characterization of the high-purity germanium detector and the establishment and verification of the efficiency calculation model for the high-purity germanium detector include: A preset point source was placed at a preset distance directly in front of a high-purity germanium detector for gamma-ray spectrum measurement. The measured detection efficiency of the full-energy peak of gamma rays at each energy level was calculated. Specifically, for energies of [energy value missing], [efficiency details missing]. of X-rays, measured detection efficiency of the full-energy peak satisfy: in, For the preset point source in energy The net peak area of ​​the all-energy peak at that location. To preset the activity of the point source, For the preset point source in energy Branch ratio at point, Preset point source measurement time; A Monte Carlo simulation model was established to calculate the efficiency of a high-purity germanium detector, and the full-energy peak simulated detection efficiency of gamma rays at various energies was calculated. ; By adjusting the parameters of the high-purity germanium detector crystal in the high-purity germanium detector efficiency calculation model, the efficiency of gamma rays at each energy level is improved. and The relative deviation is less than 2%, thus obtaining a verified high-purity germanium detector efficiency calculation model.

7. The method according to claim 5, characterized in that, Nuclide In energy Net count rate at the location With activity concentration satisfy: in, The radioactive steel ingot to be tested Nuclides in energy spectrum In energy The net peak area of ​​the all-energy peak at that location. Nuclide in the background energy spectrum In energy The net peak area of ​​the all-energy peak at that location. The radioactive steel ingot to be tested Energy spectroscopy measurement time, The baseline measurement time, nuclide In energy Branch ratio at point, For the quality of steel ingots, nuclide activity concentration, nuclide Total activity.

8. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the program is executed by the processor, it implements the method described in any one of claims 5-7.

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