Neutron dose response determination method and device, storage medium and product

Abstract

The invention provides a neutron dose response determination method and device, a storage medium and a product. The method comprises the following steps: obtaining a first neutron energy spectrum for a first emergence angle and a second neutron energy spectrum for a second emergence angle, wherein the second emergence angle is different from the first emergence angle; determining an energy spectrum correction factor based on the first neutron energy spectrum and the second neutron energy spectrum; obtaining a first indicating value of the neutron dose measurement equipment to be calibrated for the first emergence angle and a second indicating value of the neutron dose measurement equipment to be calibrated for the second emergence angle; determining a dose measurement value of the neutron dose measurement equipment to be calibrated based on the energy spectrum correction factor, the first indication value and the second indication value; and determining the neutron dose response of the neutron dose measurement equipment to be calibrated based on the dose measurement value and the agreed quantity value.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of neutron dose measurement, and in particular to a method and device for determining neutron dose response, a storage medium and a product. BACKGROUND

[0002] With the increasing demand for space radiation detection, proton / heavy ion therapy or other high-energy charged particle accelerator neutron radiation protection, in order to ensure the safety of personnel and the environment, it is necessary to accurately measure the neutron dose during the operation of these high-energy particle accelerators. However, there is no effective solution in the related art for the problem that a neutron dose measurement device covering a megaelectron volt (MeV) energy range (for example, an energy range above 20 MeV) is difficult to calibrate. SUMMARY

[0003] The embodiments of the present application provide a method and device for determining neutron dose response, a storage medium and a product, which can solve the problem that a neutron dose measurement device covering a megaelectron volt (MeV) energy range (for example, an energy range above 20 MeV) is difficult to calibrate.

[0004] The technical solutions of the embodiments of the present application are implemented as follows: The embodiments of the present application provide a method for determining neutron dose response, which comprises: obtaining a first neutron energy spectrum for a first exit angle and a second neutron energy spectrum for a second exit angle different from the first exit angle; determining an energy spectrum correction factor based on the first neutron energy spectrum and the second neutron energy spectrum; obtaining a first indication value of a to-be-calibrated neutron dose measurement device for the first exit angle and a second indication value for the second exit angle; determining a dose measurement value of the to-be-calibrated neutron dose measurement device based on the energy spectrum correction factor, the first indication value and the second indication value; determining a neutron dose response of the to-be-calibrated neutron dose measurement device based on the dose measurement value and a conventional value.

[0005] In some example embodiments, the determining of the energy spectrum correction factor based on the first neutron energy spectrum and the second neutron energy spectrum comprises: determining an energy spectrum difference value between the first neutron energy spectrum and the second neutron energy spectrum; adding a ratio between the energy spectrum difference value and the first neutron energy spectrum to a preset value to obtain the energy spectrum correction factor.

[0006] In some example embodiments, the determining the dose measurement value of the neutron dose measurement device to be calibrated based on the energy spectrum correction factor, the first indication value and the second indication value comprises: calculating a product of the second indication value and the energy spectrum correction factor; determining a difference between the first indication value and the product as the dose measurement value.

[0007] In some example embodiments, the determining the neutron dose response of the neutron dose measurement device to be calibrated based on the dose measurement value and the agreed value comprises: determining a ratio between the dose measurement value and the agreed value as the neutron dose response.

[0008] In some example embodiments, the first neutron energy spectrum and the second neutron energy spectrum are neutron energy spectra in an energy range other than peak neutrons.

[0009] In some example embodiments, the neutron energy spectrum is generated by a Li(p, n) Be nuclear reaction. 7 Li(p, n) 7 Be nuclear reaction.

[0010] In some example embodiments, the neutron dose measurement device to be calibrated comprises a neutron dose measurement device suitable for a target energy range, and the target energy range is an energy range greater than 20 MeV.

[0011] Embodiments of the present application provide an electronic device, which comprises: a memory configured to store computer executable instructions or computer programs; a processor configured to execute the computer executable instructions or computer programs stored in the memory to implement the method for determining a neutron dose response provided by embodiments of the present application.

[0012] Embodiments of the present application provide a computer readable storage medium storing computer programs or computer executable instructions, which are executed by a processor to implement the method for determining a neutron dose response provided by embodiments of the present application.

[0013] Embodiments of the present application provide a computer program product comprising computer programs or computer executable instructions, which are executed by a processor to implement the method for determining a neutron dose response provided by embodiments of the present application.

[0014] The method, device, storage medium and product for determining neutron dose response provided by the embodiments of the present application can determine a spectrum correction factor by acquiring neutron energy spectrum under different exit angles, correct the indication of the neutron dose measurement device to be calibrated under the different exit angles in combination with the spectrum correction factor, eliminate the interference caused by the nuclear reaction itself, and make the obtained dose measurement value of the neutron dose measurement device to be calibrated deduct the influence of the nuclear reaction itself on the neutron dose measurement device to be calibrated. Finally, based on the accurate dose measurement value of the neutron dose measurement device to be calibrated and the known conventional value, the accurate neutron dose response of the neutron dose measurement device to be calibrated can be obtained. In this way, by measuring and correcting under different exit angles, the influence of the nuclear reaction itself on the response calibration of the neutron dose measurement device to be calibrated can be deducted, the accurate neutron dose response can be determined without the calibration response function of the neutron dose measurement device to be calibrated, thereby realizing the accurate calibration of the neutron dose measurement device in the high-energy neutron environment, simplifying the calibration process, and improving the calibration accuracy. BRIEF DESCRIPTION OF DRAWINGS

[0015] Figure 1 A flowchart of a method for determining neutron dose response provided by the embodiments of the present application; Figure 2 A distribution diagram of neutron energy spectrum under different exit angles in the embodiments of the present application; Figure 3 A structure diagram of an electronic device provided by the embodiments of the present application. DETAILED DESCRIPTION

[0016] In order to make the purposes, technical solutions and advantages of the present application clearer, the present application will be further described in detail below with reference to the drawings, and the described embodiments should not be regarded as limiting the present application. All other embodiments obtained by those skilled in the art without making creative efforts fall within the scope of protection of the present application.

[0017] In the following description, "some embodiments" are related to a subset of all possible embodiments, but it can be understood that "some embodiments" can be the same subset or different subsets of all possible embodiments, and can be combined with each other without conflict.

[0018] In the following description, the terms "first\second\third" are only to distinguish similar objects, and do not represent a specific order of the objects. It can be understood that "first\second\third" can be interchanged in a specific order or sequence as allowed, so that the embodiments of the present application described herein can be implemented in an order other than that illustrated or described herein.

[0019] In this document, the term "one or more" means any combination of at least two of a plurality of elements, such as one or more of A, B, and C, which can mean any one or more elements selected from the set consisting of A, B, and C. The term "one or more" means any one of a plurality of elements or any combination of at least two of a plurality of elements, such as one or more of A, B, and C, which can mean any one or more elements selected from the set consisting of A, B, and C.

[0020] In the embodiments of this application, the terms "module," "unit," or "component" refer to a computer program or part of a computer program that has a predetermined function and works with other related parts to achieve a predetermined goal, and can be implemented wholly or partially using software, hardware (such as processing circuitry or memory), or a combination thereof. Similarly, a processor (or multiple processors or memory) can be used to implement one or more modules or units. Furthermore, each module or unit can be part of an overall module or unit that includes the functionality of that module or unit.

[0021] Unless otherwise defined, all technical and scientific terms used in the embodiments of this application have the same meaning as commonly understood by one of ordinary skill in the art. The terminology used in the embodiments of this application is for the purpose of describing the embodiments of this application only and is not intended to limit this application.

[0022] In the implementation of this application, the collection and processing of relevant data should strictly comply with the requirements of relevant laws and regulations, obtain the informed consent or separate consent of the personal information subject, and carry out subsequent data use and processing within the scope of laws and regulations and the authorization of the personal information subject.

[0023] Before providing a further detailed description of the embodiments of this application, the nouns and terms involved in the embodiments of this application will be explained below, and the nouns and terms involved in the embodiments of this application shall be interpreted as follows.

[0024] With the increasing prevalence of applications in space radiation detection, proton / heavy ion therapy, and other high-energy charged particle accelerators, the demand for neutron radiation protection is growing stronger. For example, the Northwest Institute of Nuclear Technology has built a 200 MeV proton accelerator; the "Space Environment Ground Simulation Facility" built by Harbin Engineering University mainly includes a proton / heavy ion accelerator with a maximum energy of 300 MeV, used to simulate the space environment and conduct irradiation experiments on biological organisms and devices under multi-factor coupling; the China Spallation Neutron Source can produce neutron energies up to 200 MeV. Furthermore, more than 16 proton / heavy ion therapy hospitals in China have obtained medical licenses, and more than 30 proton / heavy ion hospitals are under construction or in preparation. These hospitals use proton energies of approximately 200 MeV to 300 MeV. During the operation of these high-energy particle accelerators, neutron dose monitoring is required around their laboratories to ensure the safety of personnel and the environment. Currently, dose monitoring for the aforementioned accelerators primarily employs "extended neutron ambient dose equivalent (rate) meters" with added heavy metal components. However, there is no suitable dose response calibration method for such dosimeters in the megaelectron volt (MeV) energy range (e.g., above 20 MeV). Accurate neutron dose measurement is crucial for ensuring personnel and environmental safety, and accurate neutron dose response calibration is an important prerequisite for ensuring accurate neutron dose results.

[0025] Due to the unique nature of neutron dose measurement, the performance of neutron detectors is strongly correlated with neutron energy, especially in the megaelectronvolt (MeV) energy range (e.g., above 20 MeV), where the ambient dose equivalent produced by neutrons is several times or even tens of times greater than in lower energy ranges. Therefore, in environments with high-energy neutrons, neutrons in the megaelectronvolt (MeV) energy range (e.g., above 20 MeV) contribute significantly to the dose, and thus, the accuracy of the neutron dose response in the megaelectronvolt (MeV) energy range (e.g., above 20 MeV) greatly affects the accuracy of the overall neutron dose monitoring results. However, there is currently no effective solution to the problem of calibrating neutron dose measurement equipment covering the megaelectronvolt (MeV) energy range (e.g., above 20 MeV).

[0026] at present, 7 Li(p, n) 7 Be nuclear reactions are the mainstream method for generating monoenergetic neutron reference radiation fields in the megaelectronvolt (MeV) energy range (e.g., above 20 MeV). The inventors of this application have discovered that... 7 Li(p, n) 7In the neutron radiation field produced by the Be nuclear reaction, only about 50% consists of monoenergetic neutrons; the remaining 50% consists of neutrons of other energies, potentially covering the entire energy range from 0.025 eV to peak energy neutrons. Since neutron dosimetry equipment often uses thermal neutron detectors as its core detector, low-energy neutrons, due to their higher reaction cross-section, can interfere with the calibration of neutron dosimetry equipment, affecting calibration accuracy.

[0027] To address this, embodiments of this application provide a method, apparatus, storage medium, and product for determining neutron dose response. By measuring and correcting from different angles and deducting the influence of the nuclear reaction itself on the response calibration of the neutron dose measurement device to be calibrated, an accurate neutron dose response can be determined even without the calibration response function of the neutron dose measurement device to be calibrated (such as a neutron dosimeter). This solves the problem of calibrating neutron dose measurement devices with energy ranges covering the megaelectron volt (MeV) energy region (e.g., energy regions above 20 MeV), thereby simplifying the calibration process and improving calibration accuracy.

[0028] In some exemplary embodiments, the neutron dose response determination method provided in the various embodiments of this application is applicable to the determination of neutron dose response in a monoenergetic neutron reference radiation field in the megaelectronvolt (MeV) energy range (e.g., energy range above 20 MeV), and the calibration of neutron dose measurement equipment in the megaelectronvolt (MeV) energy range (e.g., energy range above 20 MeV).

[0029] Figure 1 This application provides a flowchart illustrating a method for determining neutron dose response, which will be discussed below in conjunction with... Figure 1 Please provide an explanation. For example... Figure 1 As shown, the method for determining the neutron dose response may include the following steps S101 to S105: Step S101: Obtain the first neutron energy spectrum for the first emission angle and the second neutron energy spectrum for the second emission angle, which are different from the first emission angle.

[0030] Step S102: Determine the energy spectrum correction factor based on the first neutron energy spectrum and the second neutron energy spectrum.

[0031] Step S103: Obtain the first reading of the neutron dose measurement device to be calibrated for the first emission angle and the second reading for the second emission angle.

[0032] Step S104: Based on the energy spectrum correction factor, the first reading, and the second reading, determine the dose measurement value of the neutron dose measurement device to be calibrated.

[0033] Step S105: Determine the neutron dose response of the neutron dose measurement device to be calibrated based on the dose measurement value and the agreed value.

[0034] The neutron energy spectrum can represent the energy distribution of neutrons, and can be expressed as the probability density of neutron energy.

[0035] The energy spectrum correction factor is used to characterize the influence of nuclear reactions on neutron dose measurement results and can be a quantitative parameter for the differences in neutron energy spectra at different emission angles. By introducing the energy spectrum correction factor, interference in nuclear reactions can be subtracted.

[0036] In some exemplary embodiments, any of the following neutron energy spectrum measurement methods can be used to obtain a first neutron energy spectrum for a first emission angle and a second neutron energy spectrum for a second emission angle. For example, neutron energy spectrum measurement methods may include, but are not limited to, the time-of-flight method, spectral analysis algorithms, recoil proton methods, nuclear reaction detectors, and threshold detector methods. Specifically, the time-of-flight method can refer to determining the neutron energy spectrum by measuring the neutron flight time; the spectral analysis algorithm can refer to measuring the neutron energy spectrum using a multi-sphere spectrometer; the recoil proton method can refer to calculating the neutron energy spectrum by measuring the number and energy spectrum of recoil protons; the nuclear reaction detector method can refer to obtaining the neutron energy spectrum using the pulse amplitude of the charged particle products of the 6Li(n,α)T or 3He(n,p)T reaction; and the threshold detector method can calculate the neutron energy spectrum by measuring the radioactivity of a specific nuclide activated by a neutron.

[0037] In some exemplary embodiments, the first emission angle can be a 0° emission angle, that is, the same direction as the proton.

[0038] In some exemplary embodiments, the second emission angle can be a non-0° emission angle, such as greater than 0° and less than 90°. For example, the second emission angle can be a 5° emission angle, a 10° emission angle, a 15° emission angle, a 16° emission angle, a 20° emission angle, a 25° emission angle, a 30° emission angle, a 60° emission angle, a 75° emission angle, an 85° emission angle, etc.

[0039] Among them, neutron dose measurement equipment to be calibrated refers to neutron dose measurement equipment that needs calibration, and neutron dose measurement equipment without a calibration response function. Neutron dose measurement equipment is an instrument used to measure the dose equivalent around neutrons, and typically includes types such as thermal neutron detectors.

[0040] Among them, the dose measurement value of the neutron dose measurement device to be calibrated is used to characterize the measurement result of the neutron dose measurement device to be calibrated after deducting the influence of the nuclear reaction itself.

[0041] The agreed-upon value refers to the actual neutron injection rate at the measurement location (such as the test point), and is a standard value. For example, the agreed-upon value could be the actual neutron injection rate at a distance of 1 meter from the accelerator in the test laboratory.

[0042] Thus, in the method for determining the neutron dose response provided in this application, the energy spectrum correction factor is determined by obtaining the neutron energy spectrum at two different emission angles. This correction factor is then used to correct the instrument readings of the neutron dose measurement device to be calibrated at these two different emission angles. This eliminates interference from the nuclear reaction itself, ensuring that the dose measurement value of the neutron dose measurement device to be calibrated is free from the influence of the nuclear reaction. Finally, based on the accurate dose measurement value of the neutron dose measurement device to be calibrated and the known conventional value, the accurate neutron dose response of the neutron dose measurement device to be calibrated can be obtained. In this way, by measuring and correcting at different emission angles and eliminating the influence of the nuclear reaction itself on the response calibration of the neutron dose measurement device to be calibrated, an accurate neutron dose response can be determined even without calibrating the response function of the neutron dose measurement device to be calibrated (such as a neutron dosimeter). This achieves accurate calibration of the neutron dose measurement device in a high-energy neutron environment, simplifies the calibration process, and improves calibration accuracy.

[0043] In some exemplary embodiments, in order to more easily subtract the influence of low-energy neutrons in the nuclear reaction itself on calibration, step S101, obtaining a first neutron energy spectrum for a first emission angle and a second neutron energy spectrum for a second emission angle, may include the following steps: Step S1011: At the measurement position of the first emission angle, measure the original neutron energy spectrum for the first emission angle; Step S1012: Obtain a portion of the neutron energy spectrum in the energy range other than the peak neutron in the original neutron energy spectrum for the first emission angle, as the first neutron energy spectrum for the first emission angle; Step S1013: At the measurement position of the second emission angle, which is different from the first emission angle, measure the original neutron energy spectrum for the second emission angle; Step S1014: Obtain a portion of the neutron energy spectrum in the energy range other than the peak neutron in the original neutron energy spectrum for the second emission angle, as the second neutron energy spectrum for the second emission angle.

[0044] In this way, the first neutron energy spectrum for the first emission angle and the second neutron energy spectrum for the second emission angle can be obtained.

[0045] In the megaelectronvolt (MeV) energy range (e.g., above 20 MeV), it is widely used both domestically and internationally. 7 Li(p, n) 7 Be nuclear reactions are neutron-producing reactions. The inventors of this application have discovered that: 7 Li(p, n) 7 The advantages of Be nuclear reactions in the megaelectronvolt (MeV) energy range (e.g., above 20 MeV) are: 7 Li(p, n)7 Be nuclear reactions produce neutrons with good monochromaticity. This is particularly true in the megaelectronvolt (MeV) energy range (e.g., above 20 MeV). 7 Li(p, n) 7 The Be reaction mechanism consists of direct interaction and complex nucleus interaction. The direct interaction is primarily a knockdown mechanism, producing neutrons with forward momentum and high energy, forming the high-energy peak neutron component of the quasi-monoenergetic neutron reference radiation field. The complex nucleus interaction mainly produces evaporated neutrons from an evaporation model, with an almost isotropic emission angle distribution. The neutron energy component is predominantly continuous, consisting of low- to medium-energy neutrons, forming the continuous background of the quasi-monoenergetic neutron reference radiation field. With a relatively constant number of evaporated neutrons from complex nuclei, a smaller emission angle results in a larger proportion of neutrons produced by direct interaction; conversely, with a relatively constant number of evaporated neutrons from complex nuclei, a larger emission angle results in a smaller proportion of neutrons produced by direct interaction. The inventors of this application have also discovered that: 7 Li(p, n) 7 In the neutron energy spectrum distributions of Be nuclear reactions at two different emission angles, the differences are small in the energy range excluding peak neutrons (e.g., below 90 MeV). However, in the peak neutron energy range (e.g., 90 MeV to 100 MeV), the energy spectrum distributions at the two different emission angles show significant differences. Therefore, neutron-generating reactions employ... 7 Li(p, n) 7 Taking the Be nuclear reaction as an example, to easily subtract the influence of low-energy neutrons in the nuclear reaction itself on calibration, the first neutron energy spectrum for the first emission angle can be a portion of the neutron energy spectrum within the energy range excluding peak neutrons from the original neutron energy spectrum for the first emission angle; similarly, the second neutron energy spectrum for the second emission angle can be a portion of the neutron energy spectrum within the energy range excluding peak neutrons from the original neutron energy spectrum for the second emission angle. Thus, the energy spectrum correction factor determined based on the first and second neutron energy spectra can be used to characterize the degree of influence of low-energy neutrons in the nuclear reaction on the dose measurement results. Based on this energy spectrum correction factor, the influence of low-energy neutrons in the nuclear reaction itself on calibration can be subtracted relatively easily.

[0046] In some exemplary embodiments, the neutron-generating reaction employs 7 Li(p, n) 7 Taking a Be nuclear reaction as an example, with a first emission angle of 0° and a second emission angle of 16°... Figure 2 This is a schematic diagram showing the distribution of neutron energy spectra at different emission angles in an embodiment of this application, as shown below. Figure 2 As shown, in Figure 2 In the middle, the left vertical axis represents the spectral annotation (unit: 10). 3 cm-2 MeV -1 The horizontal axis represents the neutron energy range (unit: MeV), the dashed line represents the neutron energy spectrum distribution at the first emission angle, and the solid line represents the neutron energy spectrum distribution at the second emission angle. From Figure 2 As can be seen, in the energy range below 90 MeV (i.e., the energy range excluding peak neutrons), the energy spectrum distribution of the two different emission angles is relatively similar; however, in the energy range of 90 MeV to 100 MeV (i.e., the peak neutron energy range), the energy spectrum distribution of the two different emission angles is significantly different. Therefore, in order to easily subtract the influence of low-energy neutrons on calibration, the first neutron energy spectrum for the first emission angle can be a portion of the neutron energy spectrum in the energy range excluding peak neutrons from the original neutron energy spectrum for the first emission angle, and the second neutron energy spectrum for the second emission angle can be a portion of the neutron energy spectrum in the energy range excluding peak neutrons from the original neutron energy spectrum for the second emission angle.

[0047] In some exemplary embodiments, step S102, determining the energy spectrum correction factor based on the first neutron energy spectrum and the second neutron energy spectrum, may include the following steps: Step S1021: Determine the energy spectrum difference between the first neutron energy spectrum for the first emission angle and the second neutron energy spectrum for the second emission angle; Step S1022: Add the ratio between the energy spectrum difference value and the first neutron energy spectrum to the preset value to obtain the energy spectrum correction factor.

[0048] In some exemplary embodiments, the default value is 1.

[0049] In some exemplary embodiments, taking a preset value of 1 as an example, after obtaining the first neutron energy spectrum for the first emission angle and the second neutron energy spectrum for the second emission angle, the energy spectrum correction factor can be calculated by equation (1): (1); Where k represents the energy spectrum correction factor. Represents the first neutron energy spectrum. This represents the energy spectrum of the second neutron.

[0050] In some exemplary embodiments, step S103, obtaining the first indication of the neutron dose measurement device to be calibrated for the first emission angle and the second indication for the second emission angle, may include the following steps: Step S1031: Set the neutron dose measuring device to be calibrated at the measurement position of the first emission angle, and perform neutron dose measurement through the neutron dose measuring device to be calibrated to obtain the first indication value of the neutron dose measuring device to be calibrated for the first emission angle; Step S1032: Set the neutron dose measuring device to be calibrated at the measurement position of the second emission angle, and perform neutron dose measurement through the neutron dose measuring device to be calibrated to obtain the second indication value of the neutron dose measuring device to be calibrated for the second emission angle.

[0051] Thus, the first reading of the neutron dose measurement device to be calibrated for the first emission angle and the second reading for the second emission angle are obtained.

[0052] In some other exemplary embodiments, step S103, obtaining the first indication value of the neutron dose measurement device to be calibrated for the first emission angle and the second indication value for the second emission angle, may include the following steps: acquiring the first indication value of the neutron dose measurement device to be calibrated for the first emission angle and the second indication value for the second emission angle via a camera or remote interface.

[0053] In some exemplary embodiments, step S104, determining the dose measurement value of the neutron dose measurement device to be calibrated based on the energy spectrum correction factor, the first indication, and the second indication, may include the following steps: S1041: Calculate the product of the second reading and the energy spectrum correction factor; S1042: The difference between the first reading and the product is determined as the dose measurement value.

[0054] In some exemplary embodiments, after obtaining the energy spectrum correction factor, the first reading of the neutron dose measurement device to be calibrated for the first emission angle, and the second reading of the neutron dose measurement device to be calibrated for the second emission angle, the dose measurement value of the neutron dose measurement device to be calibrated can be calculated by equation (2): (2); in, This represents the dose measurement value of the neutron dosimeter to be calibrated. This indicates the first reading of the neutron dose measurement device to be calibrated for the first emission angle. This represents the second reading of the neutron dose measurement device to be calibrated for the second emission angle, and k represents the energy spectrum correction factor.

[0055] Thus, by multiplying the second reading by the energy spectrum correction factor and then subtracting it from the first reading, the interference of the nuclear reaction itself on the measurement value can be effectively eliminated, improving the accuracy of the dose measurement value and thereby enhancing the accuracy of the neutron dose response.

[0056] In some exemplary embodiments, step S105, determining the neutron dose response based on the dose measurement value and the agreed value, may include the following step: determining the ratio between the dose measurement value and the agreed value as the neutron dose response.

[0057] In some exemplary embodiments, after obtaining the dose measurement value of the neutron dose measurement device to be calibrated, the neutron dose response of the neutron dose measurement device to be calibrated can be calculated by equation (3): (3); Where R represents the neutron dose response of the neutron dose measurement device to be calibrated. This represents the dose measurement value of the neutron dose measurement device to be calibrated, where H represents the conventional value.

[0058] Thus, since the dose measurement value of the neutron dose measurement device to be calibrated excludes the influence of low-energy neutrons in the nuclear reaction on the dose measurement, the accurate neutron dose response can be directly obtained by comparing the dose measurement value of the neutron dose measurement device to be calibrated with the agreed value. The influence of low-energy neutrons on calibration can be excluded relatively easily without relying on complex response function construction, thus reducing the calibration complexity.

[0059] In some exemplary embodiments, the first neutron energy spectrum and the second neutron energy spectrum are neutron energy spectra within the energy range excluding peak neutrons. Since low-energy neutrons have a high reaction cross-section in nuclear reactions and are a significant interference factor in the calibration of neutron dosimetry equipment, setting the first and second neutron energy spectra to neutron energy ranges excluding peak neutrons allows the energy spectrum correction factor determined based on the first and second neutron energy spectra to better characterize the impact of low-energy neutrons on calibration. This facilitates a simpler subsequent subtraction of the impact of low-energy neutrons in nuclear reactions on dose measurement from the dose measurement values ​​of the neutron dosimetry equipment to be calibrated.

[0060] In some exemplary embodiments, the energy range of the first neutron energy spectrum and the second neutron energy spectrum can be a specific energy range. For example, the energy range of both the first neutron energy spectrum and the second neutron energy spectrum is less than 90 MeV.

[0061] In some exemplary embodiments, the neutron energy spectrum is utilized 7 Li(p, n) 7 Produced by Be nuclear reactions.

[0062] In some exemplary embodiments, the neutron dose measurement device to be calibrated is suitable for 7 Li(p, n) 7 Neutron dose measurement of the quasi-monoenergetic neutron reference radiation field generated by the Be nuclear reaction.

[0063] In some exemplary embodiments, the neutron dose measurement device to be calibrated may include: a neutron dose measurement device suitable for a target energy range, wherein the target energy range is an energy range greater than 20 MeV.

[0064] In some exemplary embodiments, the target energy range applicable to the neutron dose measurement device to be calibrated may include, but is not limited to, 20 MeV, 50 MeV, 60 MeV, 80 MeV, 90 MeV, etc.

[0065] In some exemplary embodiments, the neutron dose measurement device to be calibrated may include, but is not limited to, any one of a neutron dose equivalent (rate) meter, a personal dosimeter, or an energy spectrometer. For example, the neutron dose measurement device to be calibrated may be a high-energy neutron dose equivalent (rate) meter, a personal dosimeter, or an energy spectrometer suitable for an energy range covering energy regions above 20 MeV.

[0066] In some exemplary embodiments, after calibrating the neutron dose measurement device to be calibrated through the above steps S101 to S105 and obtaining the neutron dose response of the neutron dose measurement device, the method may further include: measuring the neutron dose in other test environments using the neutron dose measurement device to obtain the measurement results of other test environments; multiplying the measurement results of other test environments with the neutron dose response of the neutron dose measurement device to obtain the actual measurement results of other test environments.

[0067] The implementation process of the embodiments of this application in a practical application scenario will be described below with reference to exemplary application examples.

[0068] This application proposes an application embodiment of a calibration method for neutron dose response based on collimated beams. As an example, this method is applicable to the calibration of neutron dose response in neutron dose measurement devices such as high-energy neutron dose equivalent (rate) meters, personal dosimeters, or energy spectrometers, covering energy ranges covering the megaelectron volt (MeV) energy region (e.g., above 20 MeV). As another example, this method is applicable to... 7 Li(p, n) 7 Calibration of the neutron dose response of a neutron dose measurement device for quasi-monoenergetic neutron reference radiation generated by the Be nuclear reaction.

[0069] In some exemplary embodiments, taking the first emission angle as a 0° emission angle and the second emission angle as another emission angle different from the 0° emission angle, the method may include the following steps: Step S1: Obtain the neutron energy spectrum at different emission angles. The neutron energy spectrum at different emission angles includes: the neutron energy spectrum within the energy range excluding peak neutrons at a 0° emission angle (as the first neutron energy spectrum). ,like Figure 2 The portion of the neutron energy spectrum with energies less than 90 MeV at the first emission angle, and the neutron energy spectrum in the energy range other than the peak neutron at other emission angles (as the second neutron energy spectrum). ,like Figure 2(The portion of the neutron energy spectrum with energies less than 90 MeV at the second emission angle). Step S2, taking a preset value of 1 as an example, calculate the neutron energy spectrum within the energy range excluding peak neutrons at a 0° emission angle (as the first neutron energy spectrum). ) and other neutron energy spectra in the energy range other than peak neutrons at other emission angles (as a second neutron energy spectrum) The energy spectrum correction factor k is calculated using the above formula (1); Step S3: Place the neutron dose measuring device to be calibrated at a 0° emission angle and other emission angles for measurement, and obtain the reading of the neutron dose measuring device at a 0° emission angle (as the first reading) and the reading of the neutron dose measuring device at other emission angles (as the second reading). Step S4: Based on the energy spectrum correction factor k and the reading of the neutron dose measurement device to be calibrated at a 0° emission angle (as the first reading)... ) and the readings of the neutron dose measurement device to be calibrated at other exit angles (as a second reading) The dose measurement value of the neutron dose measurement device to be calibrated after subtracting low-energy neutrons is calculated by formula (2) above. (i.e., the dose measurement value after deducting the background). Step S5: Based on the dose measurement value after subtracting low-energy neutrons from the neutron dose measurement equipment to be calibrated. The neutron dose response of the neutron dose measurement device to be calibrated is calculated by the above formula (3) using the agreed value H of the test point.

[0070] Thus, in the method for determining the neutron dose response provided in this application, after obtaining the neutron energy spectrum at different emission angles, an energy spectrum correction factor is determined based on the neutron energy spectrum at different emission angles; then, after obtaining the readings of the neutron dose measurement device to be calibrated at different emission angles, the dose measurement value of the neutron dose measurement device to be calibrated after deducting the influence of low-energy neutrons in the nuclear reaction is determined based on the energy spectrum correction factor and the readings of the neutron dose measurement device to be calibrated at different emission angles; finally, based on the dose measurement value of the calibrated neutron dose measurement device after deducting the influence of low-energy neutrons in the nuclear reaction and the agreed value of the test point, the neutron dose response of the neutron dose measurement device to be calibrated is determined. In this way, even without neutron dose measurement equipment to calibrate the response function, the influence of low-energy neutrons in the nuclear reaction itself on the response calibration of the neutron dose measurement equipment to be calibrated can be easily eliminated by measuring, correcting and calculating at different emission angles. This solves the problem of calibrating neutron dose measurement equipment with an energy range covering the megaelectron volt (MeV) energy region (e.g., energy regions above 20 MeV), thereby simplifying the calibration process and improving calibration accuracy.

[0071] Embodiments of this application provide an electronic device that may include: Memory is used to store executable instructions or computer programs. When a processor executes computer-executable instructions or computer programs stored in memory, it implements the neutron dose response determination method provided in one or more embodiments of this application.

[0072] Figure 3 This is a schematic diagram of the structure of an electronic device provided in an embodiment of this application. This electronic device can be applied to... Figure 1 A corresponding embodiment provides a method for determining a neutron dose response. For example... Figure 3 As shown, the electronic device 300 may include a processor 301, a memory 302, and a bus system 303. The various components in the electronic device 300 are coupled together via the bus system 303. Wherein: Bus system 303 is used to realize the communication connection between processor 301 and memory 302; Memory 302 is used to store computer-executable instructions or computer programs; When the processor 301 executes computer-executable instructions or computer programs stored in the memory 302, it implements the method for determining the neutron dose response in one or more exemplary embodiments described above.

[0073] In some exemplary embodiments, the bus system 303 may include, in addition to a data bus, a power bus, a control bus, and a status signal bus, etc. However, for the sake of clarity, in... Figure 3 The general designated all buses as Bus System 303.

[0074] In some exemplary embodiments, the electronic device may be a personal computer, a computer, a server, etc. For example, the server may be a standalone physical server, a server cluster or distributed system consisting of multiple physical servers, or a cloud server that provides cloud computing services, etc.

[0075] In some exemplary embodiments, the processor may be an integrated circuit chip with signal processing capabilities, such as a general-purpose processor, a digital signal processor (DSP), or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc., wherein the general-purpose processor may be a microprocessor or any conventional processor, etc.

[0076] This application provides a computer-readable storage medium storing computer-executable instructions or a computer program. When the computer-executable instructions or the computer program are executed by a processor, the neutron dose response determination method provided in this application can be implemented. For example, ... Figure 1 The method for determining the neutron dose response is shown.

[0077] This application provides a computer program product, which includes a computer program or computer-executable instructions. When the computer-executable instructions or the computer program are executed by a processor, the method for determining the neutron dose response provided in this application can be implemented. For example, ... Figure 1 The method for determining the neutron dose response is illustrated. For example, the computer program or computer-executable instructions are stored in a computer-readable storage medium, and the processor of the electronic device reads the computer program or computer-executable instructions from the computer-readable storage medium and executes the computer program or computer-executable instructions, causing the electronic device to perform the method for determining the neutron dose response provided in the embodiments of this application.

[0078] In some exemplary embodiments, the aforementioned computer-readable storage medium / memory may be a read-only memory (ROM), a programmable read-only memory (PROM), an erasable programmable read-only memory (EPROM), an electrically erasable programmable read-only memory (EEPROM), a magnetic random access memory (FRAM), a flash memory, a magnetic surface memory, an optical disc, or a compact disc read-only memory (CD-ROM), etc.; or it may be various terminals including one or any combination of the above-mentioned memories, such as mobile phones, computers, tablet devices, personal digital assistants, etc.

[0079] In some embodiments, a computer program or computer-executable instructions may take the form of a program, software, software module, script, or code, written in any form of programming language (including compiled or interpreted languages, or declarative or procedural languages), and may be deployed in any form, including as a standalone program or as a module, component, subroutine, or other unit suitable for use in a computing environment.

[0080] As an example, a computer program or computer-executable instructions may, but not necessarily, correspond to a file in a file system. It may be stored as part of a file that holds other programs or data, for example, in one or more scripts in a Hyper Text Markup Language (HTML) document, in a single file dedicated to the program in question, or in multiple collaborating files (e.g., a file that stores one or more modules, subroutines, or code sections).

[0081] As an example, a computer program or computer-executable instructions may be deployed to execute on one electronic device, or on multiple electronic devices located at one location, or on multiple electronic devices distributed across multiple locations and interconnected by a communication network.

[0082] It should be noted that the descriptions of the above device, storage medium, or product embodiments are similar to the descriptions of the above method embodiments, and have similar beneficial effects. For technical details not disclosed in the device, storage medium, or product embodiments of this application, those skilled in the art should refer to the descriptions of the method embodiments of this disclosure for understanding. Further details will not be repeated here.

[0083] The features disclosed in the several methods, devices, storage media or product embodiments provided in this application can be arbitrarily combined without conflict to obtain new method embodiments, devices, storage media or product embodiments.

[0084] The above description is merely an embodiment of this application and is not intended to limit the scope of protection of this application. Any modifications, equivalent substitutions, and improvements made within the spirit and scope of this application are included within the scope of protection of this application.

Claims

1. A method for determining neutron dose response, characterized in that, The method includes: A first neutron energy spectrum for a first emission angle and a second neutron energy spectrum for a second emission angle are obtained, wherein the second emission angle is different from the first emission angle. Based on the first neutron energy spectrum and the second neutron energy spectrum, determine the energy spectrum correction factor; Obtain a first reading of the neutron dose measurement device to be calibrated for the first emission angle and a second reading for the second emission angle; Based on the energy spectrum correction factor, the first reading, and the second reading, the dose measurement value of the neutron dose measurement device to be calibrated is determined; Based on the dose measurement value and the agreed value, the neutron dose response of the neutron dose measurement device to be calibrated is determined.

2. The method according to claim 1, characterized in that, The determination of the energy spectrum correction factor based on the first neutron energy spectrum and the second neutron energy spectrum includes: Determine the energy spectrum difference between the first neutron energy spectrum and the second neutron energy spectrum; The energy spectrum correction factor is obtained by adding the ratio between the energy spectrum difference value and the first neutron energy spectrum to a preset value.

3. The method according to claim 1, characterized in that, The step of determining the dose measurement value of the neutron dose measurement device to be calibrated based on the energy spectrum correction factor, the first indication, and the second indication includes: Calculate the product of the second indicated value and the energy spectrum correction factor; The difference between the first indicated value and the product is determined as the dose measurement value.

4. The method according to claim 1, characterized in that, The step of determining the neutron dose response of the neutron dose measurement device to be calibrated based on the dose measurement value and the agreed-upon value includes: The ratio between the measured dose value and the predetermined dose value is determined as the neutron dose response.

5. The method according to any one of claims 1 to 4, characterized in that, The first neutron energy spectrum and the second neutron energy spectrum are neutron energy spectra in the energy range other than peak neutrons.

6. The method according to any one of claims 1 to 4, characterized in that, The neutron energy spectrum is utilized 7 Li(p,n) 7 Produced by Be nuclear reactions.

7. The method according to any one of claims 1 to 4, characterized in that, The neutron dose measurement device to be calibrated includes: a neutron dose measurement device suitable for a target energy range, wherein the target energy range is an energy range greater than 20 MeV.

8. An electronic device, characterized in that, The electronic device includes: Memory is used to store executable instructions or computer programs. A processor, when executing computer-executable instructions or computer programs stored in the memory, implements the method as described in any one of claims 1 to 7.

9. A computer-readable storage medium storing a computer program or computer-executable instructions, characterized in that, When the computer program or computer-executable instructions are executed by a processor, the method as described in any one of claims 1 to 7 is implemented.

10. A computer program product comprising a computer program or computer-executable instructions, characterized in that, When the computer program or computer-executable instructions are executed by a processor, the method as described in any one of claims 1 to 7 is implemented.

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