Material testing methods, apparatuses, devices, media, and products

Abstract

This application discloses a material testing method, apparatus, equipment, medium, and product. The material testing method includes: controlling a target neutron source to emit raw neutron beams into moderators of various thicknesses, so that the raw neutron beams are moderated by the moderators of different thicknesses, generating multiple neutron beams; obtaining the number of non-thermal neutrons and the total number of neutrons in the neutron beams; determining the number of thermal neutrons and the proportion of thermal neutrons corresponding to each neutron beam based on the number of non-thermal neutrons and the total number of neutrons; identifying the neutron beam with the highest number of thermal neutrons and the highest proportion of thermal neutrons from the multiple neutron beams as the target neutron beam, and determining the thickness of the moderator corresponding to the target neutron beam as the target thickness; performing a thermal neutron shielding test on the target material based on the target moderater of the target thickness to obtain the thermal neutron shielding rate corresponding to the target material. According to the embodiments of this application, the accuracy of the thermal neutron shielding rate test results for materials can be improved.

Description

Technical Field

[0001] This application belongs to the field of nuclear technology and application technology, and in particular relates to a material testing method, apparatus, equipment, medium and product. Background Technology

[0002] Currently, the use of radioactive sources in various locations is increasing, and neutrons are widely used in fields such as nuclear power, neutron radiography, activation analysis, and radiotherapy. This has led to a growing demand for testing the shielding efficiency of neutron irradiation devices. Over the past decade, advancements in materials science have had a significant impact on radiation shielding technology, and the thermal neutron shielding efficiency of many new radiation protection materials now requires testing and characterization.

[0003] When testing the thermal neutron shielding efficiency of materials, cadmium is typically used because it has an extremely high absorption cross-section for thermal neutrons and interacts almost no with hyperthermal and fast neutrons. Based on the number of neutrons in the target neutron beam detected by a helium-3 neutron detector, the cadmium difference method is used to obtain the number of non-thermal neutrons in the target neutron beam. The difference is then used to calculate the number of thermal neutrons neutralized in the target neutron beam, thus testing the material's thermal neutron shielding efficiency. However, current technologies lack a clear selection criterion for the appropriate moderation level of the original neutron beam generated by the neutron source, leading to significant measurement errors and low accuracy in the thermal neutron shielding efficiency test results. Summary of the Invention

[0004] This application provides a material testing method, apparatus, equipment, medium, and product that can improve the accuracy of thermal neutron shielding test results for materials.

[0005] In a first aspect, embodiments of this application provide a material testing method, the method comprising:

[0006] The target neutron source is controlled to emit raw neutron beams into moderators of various thicknesses, so that the raw neutron beams are slowed down by the moderators of various thicknesses, thus generating multiple neutron beams.

[0007] Obtain the number of nonthermal neutrons and the total number of neutrons in the neutron beam;

[0008] The number of thermal neutrons and the proportion of thermal neutrons corresponding to the neutron beam are determined based on the number of non-thermal neutrons and the total number of neutrons.

[0009] From multiple neutron beams, the neutron beam with the highest number of thermal neutrons and the highest proportion of thermal neutrons is identified as the target neutron beam, and the thickness of the moderator corresponding to the target neutron beam is determined as the target thickness.

[0010] Thermal neutron shielding tests were conducted on the target material based on the target moderater based on the target thickness to obtain the thermal neutron shielding rate corresponding to the target material.

[0011] Secondly, embodiments of this application provide a material testing apparatus, the apparatus comprising:

[0012] The control module is used to control the target neutron source to emit raw neutron beams into moderators of various thicknesses, so that the raw neutron beams are slowed down by the moderators of various thicknesses to generate multiple neutron beams.

[0013] The acquisition module is used to acquire the number of non-thermal neutrons and the total number of neutrons in the neutron beam;

[0014] The first determining module is used to determine the number of thermal neutrons and the proportion of thermal neutrons corresponding to the neutron beam based on the number of non-thermal neutrons and the total number of neutrons.

[0015] The second determining module is used to determine the neutron beam with the highest number of thermal neutrons and the neutron beam with the highest proportion of thermal neutrons from multiple neutron beams, and to determine the thickness of the moderator corresponding to the target neutron beam as the target thickness.

[0016] The testing module is used to perform thermal neutron shielding tests on target materials based on the target thickness of the target moderator, and to obtain the thermal neutron shielding rate corresponding to the target material.

[0017] Thirdly, embodiments of this application provide an electronic device, which includes: a processor and a memory storing computer program instructions;

[0018] When the processor executes the computer program instructions, it implements the steps of the material testing method as described in any embodiment of the first aspect.

[0019] Fourthly, embodiments of this application provide a computer-readable storage medium storing computer program instructions that, when executed by a processor, implement the steps of the material testing method as described in any embodiment of the first aspect.

[0020] Fifthly, embodiments of this application provide a computer program product in which instructions, when executed by a processor of an electronic device, cause the electronic device to perform the steps of the material testing method as described in any embodiment of the first aspect.

[0021] The material testing method, apparatus, equipment, medium, and product in this application embodiment emits raw neutron beams from a target neutron source onto moderators of various thicknesses. After the raw neutron beams are moderated by moderators of different thicknesses, multiple neutron beams are generated. The number of non-thermal neutrons and the total number of neutrons in the multiple neutron beams are obtained, and the number and percentage of thermal neutrons corresponding to the multiple neutron beams are determined. The neutron beam with the highest number and percentage of thermal neutrons is selected as the target neutron beam. After determining the target thickness based on the thickness of the moderator corresponding to the target neutron beam, thermal neutron shielding tests can be performed on the target material based on the target moderater of the target thickness. Thus, when performing thermal neutron shielding tests on the target material, the degree of moderation of the moderator is determined. By slowing down the target neutron source using the target moderater, a target neutron beam with a higher number and percentage of thermal neutrons can be generated. In this way, when testing the thermal neutron shielding performance of the target material, the relative error can be reduced, and the accuracy of the thermal neutron shielding rate test results of the target material can be improved. Attached Figure Description

[0022] To more clearly illustrate the technical solutions of the embodiments of this application, the accompanying drawings used in the embodiments of this application will be briefly introduced below. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0023] Figure 1 This is a schematic diagram of a material testing platform provided in an embodiment of this application;

[0024] Figure 2 This is a schematic flowchart of a material testing method provided in an embodiment of this application;

[0025] Figure 3 This is a measurement schematic diagram of the neutron beam exit port without any shielding provided in the embodiments of this application;

[0026] Figure 4 This is a measurement schematic diagram of adding a cadmium sheet shield to the neutron beam exit port according to an embodiment of this application;

[0027] Figure 5 This is a measurement schematic diagram of adding target material shielding to the neutron beam exit port provided in an embodiment of this application;

[0028] Figure 6 This is a measurement schematic diagram of simultaneously adding cadmium sheet and target material shielding to the neutron beam exit port according to an embodiment of this application;

[0029] Figure 7 This is a schematic diagram of the structure of a material testing device provided in an embodiment of this application;

[0030] Figure 8This is a schematic diagram of the structure of an electronic device provided in an embodiment of this application. Detailed Implementation

[0031] The features and exemplary embodiments of various aspects of this application will be described in detail below. To make the objectives, technical solutions, and advantages of this application clearer, the application will be further described in detail below with reference to the accompanying drawings and specific embodiments. It should be understood that the specific embodiments described herein are only intended to explain this application and not to limit it. For those skilled in the art, this application can be implemented without some of these specific details. The following description of the embodiments is merely to provide a better understanding of this application by illustrating examples.

[0032] It should be noted that, in this document, relational terms such as "first" and "second" are used merely to distinguish one entity or operation from another, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Furthermore, the terms "comprising," "including," or any other variations thereof are intended to cover non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements includes not only those elements but also other elements not expressly listed, or elements inherent to such a process, method, article, or apparatus. Without further limitations, an element defined by the phrase "comprising..." does not exclude the presence of additional identical elements in the process, method, article, or apparatus that includes said element.

[0033] Currently, when testing the thermal neutron shielding efficiency of materials, the characteristic of cadmium, which has an extremely high absorption cross section for thermal neutrons and hardly interacts with ultrathermal neutrons and fast neutrons, is usually utilized. Based on the number of neutrons in the target neutron beam detected by a helium-3 neutron detector, the cadmium difference method is used to obtain the number of non-thermal neutrons in the target neutron beam. Then, the difference is taken to obtain the number of thermal neutrons neutralized in the target neutron beam, and the thermal neutron shielding efficiency of the material is tested in this way.

[0034] The thermal neutron shielding efficiency of materials is measured by the cadmium difference method. A primitive neutron beam is generated by a neutron source, which contains a large number of non-thermal neutrons. The number and proportion of thermal neutrons in the primitive neutron beam can be increased by slowing down the neutron source. However, in the existing technology, there is a lack of selection criteria for the appropriate slowing degree of the primitive neutron beam generated by the neutron source, which leads to a large measurement error and low accuracy of the thermal neutron shielding efficiency test results of the materials.

[0035] To address the problems in the prior art, the embodiments of this application first performed a theoretical derivation based on the cadmium difference method.

[0036] When measuring the thermal neutron shielding efficiency of a target material based on the cadmium difference method, the number of neutrons in the neutron beam can be measured by a helium-3 neutron detector. The number of neutrons N detected by the helium-3 neutron detector can be determined by the following formula (1).

[0037]

[0038] Where, φ E It is the neutron energy spectrum corresponding to the neutron beam, R E It is the detector energy response function, where N is determined by φ. E With R E E obtained from convolution min E max These are the minimum and maximum energies of a neutron, respectively. The energy response function of the detector for the same detector remains constant.

[0039] Under conditions of parallel neutron beam emission, no environmental scattering, and complete absorption of thermal neutrons by the cadmium sheet, with the distance between the helium-3 neutron detector and the neutron beam exit port fixed, where thermal neutrons can be neutrons with energies less than 0.4 eV from the neutron beam, the total number of neutrons N detected by the helium-3 neutron detector at the neutron beam exit port without any shielding can be determined. 10 The number of non-thermal neutrons N detected when a cadmium sheet is added to the neutron beam exit port 20 The total number of neutrons N detected when the neutron beam exit port is shielded by target material. 11 The number of non-thermal neutrons N detected when both the target material and cadmium sheet are used for shielding at the neutron beam exit port. 21 The relative error σ of the thermal neutron shielding efficiency of the target material can be determined by the following formula (2). thermal .

[0040]

[0041] When the number of thermal neutrons in a neutron beam is C, the corresponding number of thermal neutrons c can be detected and determined by a helium-3 neutron detector. Similarly, when the proportion of thermal neutrons in a neutron beam is P, the corresponding proportion of thermal neutrons p and the proportion of non-thermal neutrons 1-p can be detected and determined by a helium-3 neutron detector.

[0042] Furthermore, when the composition and size of the target material are determined, the equivalent transmittance of the target material to thermal and non-thermal neutrons can be determined. For example, the equivalent transmittance of the target material to thermal and non-thermal neutrons in the same neutron beam can be approximated as a constant, that is, the equivalent transmittance of the target material to thermal neutrons in the aforementioned neutron beam can be determined as a constant T. the The equivalent transmittance of non-thermal neutrons in the aforementioned neutron beam can be determined as a constant T. noth .

[0043] Thus, based on the above-mentioned thermal neutron quantity c, thermal neutron quantity ratio p, and the equivalent transmittance T of the target material to thermal neutrons... the and the equivalent transmittance T of the target material to non-thermal neutrons noth N can be expressed by the following formulas (3), (4), (5) and (6) respectively. 10 N 20 N 11 and N 21 .

[0044]

[0045]

[0046]

[0047]

[0048] Based on formulas (3), (4), (5), and (6), N in formula (2) is... 10 N 20 N 11 N 21 By performing equivalent substitution, we can obtain the simplified relative error of the following formula (7).

[0049]

[0050] Among them, T the T noth It is a constant. Let c be a constant in the range (0, 1), and let p be the number of thermal neutrons and the percentage of thermal neutrons.

[0051] According to formula (7), the relative error is determined to be a function of the number of thermal neutrons c and the proportion of thermal neutrons p as shown in formula (8).

[0052]

[0053] The domain of f(c, p) is c∈(0, ∞) and p∈(0, 1).

[0054] By taking the partial derivative with respect to c, we can obtain the following formula (9), where T the T noth Since p∈(0,1), when c∈(0,∞), f c (c, p) < 0 indicates that when the proportion of thermal neutrons p remains constant, the larger the number of thermal neutrons c, the smaller the relative error.

[0055]

[0056] By taking the partial derivative with respect to p, we can obtain the following formula (10), where T the T noth Since p ∈ (0, 1) and c ∈ (0, ∞), f p (c, p) < 0 indicates that the number of thermal neutrons c remains constant, and the larger the proportion of thermal neutrons p, the smaller the relative error.

[0057]

[0058] Therefore, through the above theoretical derivation, it can be concluded that the larger the proportion of thermal neutrons p and the number of thermal neutrons c in the neutron beam detected by the detector, the smaller the relative error of the measurement result.

[0059] Based on the conclusions derived from the above theoretical derivation, embodiments of this application provide a material testing method, apparatus, equipment, medium, and product.

[0060] The material testing method provided in this application will be described in detail below with reference to the accompanying drawings, through specific embodiments and application scenarios.

[0061] Figure 1 This is a schematic diagram of a material testing platform provided in an embodiment of this application. Figure 1 As shown, the material testing platform includes a testing system 11, a target detector 12, a neutron source shield 13, a target neutron source 14, a moderator 15, and a neutron beam exit port 16. The testing system 11 controls the target neutron source 14 to emit a raw neutron beam towards the moderator 15. After being moderated by the moderator, the raw neutron beam is emitted through the neutron beam exit port 16 towards the target detector 12, where the target detector 12 detects the number of neutrons in the beam. The neutron source shield 13 can shield most neutron radiation. A cadmium sheet or target material can be placed against the neutron beam exit port 16 to allow the target detector 12 to detect the number of neutrons under different shielding conditions, thus achieving a thermal neutron shielding rate test of the target material.

[0062] Figure 2 This is a schematic flowchart of a material testing method provided in an embodiment of this application. Figure 1 As shown, the material testing method may specifically include the following steps:

[0063] S210. Control the target neutron source to emit original neutron beams into moderators of various thicknesses, so that the original neutron beams are slowed down by the moderators of various thicknesses, thus generating multiple neutron beams.

[0064] S220. Obtain the number of nonthermal neutrons and the total number of neutrons in the neutron beam;

[0065] S230. Determine the number of thermal neutrons and the proportion of thermal neutrons corresponding to the neutron beam based on the number of non-thermal neutrons and the total number of neutrons.

[0066] S240. From multiple neutron beams, determine the neutron beam with the highest number of thermal neutrons and the highest proportion of thermal neutrons as the target neutron beam, and determine the thickness of the moderator corresponding to the target neutron beam as the target thickness.

[0067] S250. Based on the target thickness, the target moderator performs a thermal neutron shielding test on the target material to obtain the thermal neutron shielding rate corresponding to the target material.

[0068] Therefore, by controlling the target neutron source to emit raw neutron beams into moderators of varying thicknesses, multiple neutron beams are generated after each raw neutron beam is moderated by moderators of different thicknesses. The number of non-thermal neutrons and the total number of neutrons in these multiple neutron beams are obtained, and the number and percentage of thermal neutrons corresponding to each beam are determined. The neutron beam with the highest number and percentage of thermal neutrons is selected as the target neutron beam. After determining the target thickness based on the thickness of the moderator corresponding to the target neutron beam, thermal neutron shielding tests can be performed on the target material using the target moderator at that thickness. Thus, when testing the thermal neutron shielding performance of the target material, the degree of moderation of the moderator is determined. By using the target moderator to moderate the target neutron source, a target neutron beam with a higher number and percentage of thermal neutrons can be generated. This reduces relative error and improves the accuracy of the thermal neutron shielding performance test results for the target material.

[0069] The specific implementation methods for each of the above steps are described below.

[0070] In some embodiments, in S210, the test system can control the target neutron source to emit raw neutron beams into moderators of varying thicknesses. The target neutron source can be any radioactive isotope neutron source, such as an Am-Be radioactive isotope neutron source. The moderator can be a material that slows down the raw neutron beams to produce thermal neutrons, such as polyethylene. Moderators of varying thicknesses can have different slowing thicknesses; after the raw neutron beams are slowed down by moderators of different thicknesses, the resulting neutron beams contain different numbers and proportions of thermal neutrons.

[0071] In some implementations, in S220, the original neutron beam is slowed down by moderators of different thicknesses to obtain multiple neutron beams. The number of non-thermal neutrons and the total number of thermal neutrons in the neutron beams can be obtained through experimental testing to further determine the number of thermal neutrons and the proportion of thermal neutrons in the neutron beams, or the number of thermal neutrons and the proportion of thermal neutrons in the neutron beams can be determined through Monte Carlo simulation.

[0072] As an example, in order to obtain the number of non-thermal neutrons and the total number of neutrons in a neutron beam through experimental testing, the above-mentioned S220 may specifically include:

[0073] A neutron beam is emitted toward the target detector through the neutron beam exit port;

[0074] Obtain the total number of neutrons detected by the target detector without adding any shielding at the neutron beam exit port;

[0075] With a cadmium sheet added to the neutron beam exit port for shielding, the number of non-thermal neutrons detected by the target detector is obtained, where the cadmium sheet is used to absorb thermal neutrons in the neutron beam.

[0076] The target detector can be a helium-3 neutron detector. By adding a cadmium sheet to the neutron beam exit port, the high absorption cross-section of cadmium for thermal neutrons and its near-inaction with non-thermal neutrons allow the target detector to detect the number of non-thermal neutrons in the neutron beam. Thermal and non-thermal neutrons are neutrons with different energies in the neutron beam. Thermal neutrons can be those with energies less than 0.4 eV, while non-thermal neutrons can be those with energies greater than 0.4 eV.

[0077] Thus, in the experimental test, neutron beams with different slowing thicknesses were emitted to the target detector through the neutron beam exit port. Without any shielding added to the neutron beam exit port, the target detector could detect the total number of neutrons. With a cadmium sheet added to the neutron beam exit port, the target detector could detect the number of non-thermal neutrons in the neutron beam.

[0078] In some implementations, in S230, after the number of non-thermal neutrons and the total number of neutrons in the neutron beam are experimentally measured, the number of thermal neutrons c and the proportion of thermal neutrons p corresponding to the neutron beam can be determined.

[0079] As an example, the above S230 may specifically include:

[0080] Determine the difference between the total number of neutrons and the number of non-thermal neutrons, and use the difference as the number of thermal neutrons corresponding to the neutron beam;

[0081] Determine the ratio between the number of thermal neutrons and the total number of neutrons, and use this ratio as the percentage of thermal neutrons in the neutron beam.

[0082] In this way, the number of thermal neutrons c and the proportion of thermal neutrons p corresponding to multiple neutron beams with different moderation thicknesses can be determined through experimental measurement. For example, using polyethylene as the moderator, the moderation thickness is set to start from 0 and increase at certain intervals until the moderation thickness reaches 12 cm. After the target neutron source emits original neutron beams into the moderators with different moderation thicknesses, the data of the number of thermal neutrons c and the proportion of thermal neutrons p corresponding to multiple neutron beams can be obtained as shown in Table 1.

[0083] Table 1

[0084]

[0085]

[0086] In addition, the number of thermal neutrons C and the proportion of thermal neutrons P in multiple neutron beams can also be determined using the Monte Carlo method. The data obtained are shown in Table 2, where the data for the number of thermal neutrons C are normalized data.

[0087] Table 2

[0088] Slowing thickness (cm) Number of thermal neutrons C Percentage of thermal neutrons, P (%) 0 1.94E-04 15.43 2 2.05E-04 21.37 3 1.99E-04 23.03 4 1.89E-04 24.13 5 1.76E-04 24.76 …… …… ……

[0089] In some embodiments, in S240, based on the conclusions derived from the above theory, the neutron beam with the highest number of thermal neutrons and the highest percentage of thermal neutrons can be determined as the target neutron beam. That is, measuring the target material using the number and percentage of thermal neutrons corresponding to the target neutron beam minimizes the relative error and improves the accuracy of the measurement results. Furthermore, the thickness of the moderator corresponding to the target neutron beam can be determined as the target thickness, and the target neutron beam can be generated by slowing down the moderator based on the target thickness.

[0090] In some embodiments, in order to determine the target neutron beam, the above-mentioned S240 may specifically include:

[0091] For each of the multiple neutron beams, determine the product between the number of thermal neutrons and the percentage of thermal neutrons;

[0092] From multiple neutron beams, the neutron beam with the largest product value is identified as the target neutron beam.

[0093] In some specific examples, for each neutron beam in multiple neutron beams, after obtaining the number and percentage of thermal neutrons through experimental measurements as shown in Table 1 above or through Monte Carlo simulations as shown in Table 2 above, the product value between the number and percentage of thermal neutrons for each neutron beam can be determined. As shown in Table 3, corresponding to the product values ​​in Table 1 above, the target thickness corresponding to the target neutron beam is determined to be 3 cm. Similarly, as shown in Table 4, corresponding to the product values ​​in Table 2 above, the target thickness corresponding to the target neutron beam is also determined to be 3 cm.

[0094] Table 3

[0095] Slowing thickness (cm) Number of thermal neutrons c The percentage of thermal neutrons, p(%) (c×p) 0 1643 35.98 59110 2 1967 41.92 82450 3 2245 42.50 95423 4 1959 43.57 85351 5 1796 40.98 73583 …… …… …… ……

[0096] Table 4

[0097] Slowing thickness (cm) Number of thermal neutrons C Percentage of thermal neutrons, P (%) (C×P) 0 1.94E-04 15.43 2.99E-05 2 2.05E-04 21.37 4.38E-05 3 1.99E-04 23.03 4.58E-05 4 1.89E-04 24.13 4.56E-05 5 1.76E-04 24.76 4.35E-05 …… …… …… ……

[0098] Therefore, by obtaining the number of non-thermal neutrons and the total number of thermal neutrons, the number and proportion of thermal neutrons corresponding to multiple neutron beams can be determined. Based on the product of the number of thermal neutrons and the proportion of thermal neutrons, the neutron beam with the largest product value can be identified as the target neutron beam, thus determining the target thickness of the moderator. Measuring the thermal neutron shielding efficiency of the target material using the target neutron beam can reduce relative errors and improve the accuracy of the measurement results.

[0099] In some embodiments, in S250, after determining the target thickness, the thermal neutron shielding efficiency of the target material can be tested based on the target moderator with the target thickness when measuring the thermal neutron shielding efficiency.

[0100] In some embodiments, in order to obtain the thermal neutron shielding efficiency corresponding to the target material, the above-mentioned S250 may specifically include:

[0101] The target neutron source is controlled to emit a primitive neutron beam toward a target moderator of the target thickness, so that the primitive neutron beam is slowed down by the target moderator and then the target neutron beam is generated.

[0102] Based on the cadmium difference method, thermal neutron shielding tests are performed on the target material using a target neutron beam to obtain the thermal neutron shielding rate corresponding to the target material.

[0103] In testing the thermal neutron shielding efficiency of a target material, the target thickness of the target moderator can be used as the optimal moderator. The optimal moderator is used to slow down the original neutron beam of the target neutron source. Here, different neutron sources correspond to different optimal moderators.

[0104] As an example, the above-mentioned thermal neutron shielding test of a target material using a target neutron beam, based on the cadmium difference method, yields the thermal neutron shielding rate corresponding to the target material. Specifically, this can include:

[0105] The target neutron beam is emitted toward the target detector through the neutron beam exit port;

[0106] Obtain the first total number of neutrons detected by the target detector without adding any shielding to the neutron beam exit port;

[0107] With cadmium sheet shielding added to the neutron beam exit port, the number of the first non-thermal neutrons detected by the target detector is obtained, wherein the cadmium sheet is used to absorb thermal neutrons in the target neutron beam;

[0108] With target material shielding added to the neutron beam exit port, the total number of second neutrons detected by the target detector is obtained;

[0109] The number of second nonthermal neutrons detected by the target detector is obtained when cadmium sheet and target material are simultaneously added to the neutron beam exit port.

[0110] The thermal neutron shielding rate of the target material is determined based on the total number of first neutrons, the number of first non-thermal neutrons, the total number of second neutrons, and the number of second non-thermal neutrons.

[0111] Thus, the initial total number of neutrons N can be determined based on the condition that no shielding is added at the neutron beam exit port. 10 The first nonthermal neutron quantity N with cadmium shielding added to the neutron beam exit port. 20 The total number of second neutrons N when a target material shield is added to the neutron beam exit port. 11 The number of second nonthermal neutrons N when cadmium sheets and target materials are simultaneously added to the neutron beam exit port. 21 The thermal neutron shielding efficiency R of the target material is determined by the following formula (11). thermal .

[0112]

[0113] Where, N 10 -N 20 N represents the number of thermal neutrons in the target neutron beam. 11 -N 21 This indicates the number of thermal neutrons after the target neutron beam passes through the target material.

[0114] As an example, such as Figure 3 The diagram shown is a measurement schematic without any shielding added to the neutron beam exit port. Neutron beam exit port 1 emits target neutron beam 2 towards target detector 4, and the target detector detects the first total number of neutrons N. 10 The measurement showed the presence of environmentally scattered neutrons (3). For example... Figure 4 The diagram shows a measurement with a cadmium sheet shielding the neutron beam exit port. The cadmium sheet 5 is placed against the neutron beam exit port 1, and the target neutron beam 2 passes through the cadmium sheet 5 to the target detector 4. The target detector detects the first non-thermal neutron quantity N. 20 The measurement showed the presence of environmentally scattered neutrons (3). For example... Figure 5The diagram shows a measurement with a target material shielding the neutron beam exit port. The target material 6 is in contact with the neutron beam exit port 1, and the target neutron beam 2 passes through the target material 6 to the target detector 4. The target detector detects the second total number of neutrons N. 11 The measurement showed the presence of environmentally scattered neutrons (3). For example... Figure 6 The diagram shows a measurement with a cadmium sheet and target material shielding simultaneously added to the neutron beam exit port. The cadmium sheet 5 is in contact with the neutron beam exit port 1, and the target material 6 is in contact with the cadmium sheet 5. The target neutron beam 2 passes through the cadmium sheet 5 and the target material 6 to the target detector 4. The target detector detects the second non-thermal neutron quantity N. 21 During the measurement, environmental scattered neutrons 3 are present. The distance between the neutron beam exit port 1 and the target detector 4 is maintained at d throughout the measurement process.

[0115] In addition, after determining the target thickness, for the sake of rigor, a 1cm thick polyethylene can be used as the target material. Based on the multiple neutron beams obtained by slowing down the original neutron beam under different slowing thicknesses, the thermal neutron shielding efficiency of the target material is tested. The corresponding relative error is determined by formula (2), and the test data in Table 5 below can be obtained. From the test data, it can be determined that when the slowing thickness is 3cm, the relative error of the thermal neutron shielding efficiency is 4.93, which is the smallest relative error among various slowing thicknesses, consistent with the target thickness determined above. This verifies that the effect of the slowing body of the target thickness on the accuracy of the test results is definitely improved.

[0116] Table 5

[0117]

[0118]

[0119] In some embodiments, the neutron beam is scattered by the test platform and surrounding matter. The resulting environmental scattered neutrons are related to the density of the test platform and surrounding matter; the denser the test platform and surrounding matter, the more environmental scattered neutrons are generated. When measuring the thermal neutron shielding efficiency of a target material based on the cadmium difference method, systematic errors will exist due to the influence of environmental scattered neutrons on the target detector, as shown in formula (11). As shown, it can be achieved by detecting N 10 N 20 N 11 N 21 The test platform structure is consistent with the corresponding time to detect approximate environmental scattered neutrons, and then the systematic error caused by environmental scattered neutrons is reduced to the greatest extent by subtraction.

[0120] As an example, during the measurement process, the distance between the target detector and the neutron beam exit port is kept constant. The center of the target detector is located on the central axis of the target neutron beam, and the size of the target material and the cadmium sheet is slightly larger than the size of the neutron beam exit port. When adding cadmium sheet shielding to the neutron beam exit port for measurement, the cadmium sheet is placed against the neutron beam exit port. When adding target material shielding to the neutron beam exit port for measurement, the target material is placed against the neutron beam exit port. When simultaneously adding cadmium sheet and target material shielding to the neutron beam exit port for measurement, the cadmium sheet is placed against neutron beam exit port 1, and then the target material is placed against the cadmium sheet. For example... Figure 3 , Figure 4 , Figure 5 and Figure 6 As shown, when considering the systematic error introduced by the neutrons scattered by the environment, the number of neutrons measured by the target detector can include the number of neutrons in the target neutron beam and the number of neutrons scattered by the environment, as shown in the following formulas (12), (13), (14) and (15).

[0121] N 10 =N 10 ′+N 10 " (12)

[0122] N 20 =N 20 ′+N 20 " (13)

[0123] N 11 =N 11 ′+N 11 " (14)

[0124] N 21 =N 21 ′+N 21 "(15)"

[0125] Where, N 10 ′, N 20 ′, N 11 ′, N 21 ′ represents the number of neutrons in the target neutron beam under different shielding conditions, N 10 ", N 20 ", N 11 ", N 21 "" represents the number of ambient scattered neutrons under different shielding conditions. Since the target material is in contact with the cadmium sheet during measurement, the target material and cadmium sheet primarily shield the target neutron beam, while having almost no effect on ambient scattered neutrons. Therefore, it can be considered that an approximate number of ambient scattered neutrons, N, is detected. 10 "≈N 20 "≈N 11 "≈N 21By subtracting the following formula (16), the scattered neutrons in the environment can be canceled out. The calculation result is mainly obtained by the number of neutrons in the target neutron beam, which reduces the system error.

[0126]

[0127] It should be noted that the application scenarios described in the above embodiments of this application are for the purpose of more clearly illustrating the technical solutions of the embodiments of this application, and do not constitute a limitation on the technical solutions provided by the embodiments of this application. As those skilled in the art will know, with the emergence of new application scenarios, the technical solutions provided by the embodiments of this application are also applicable to similar technical problems.

[0128] Based on the same inventive concept, this application also provides a material testing device. (Specifically combined with...) Figure 7 Please provide a detailed explanation.

[0129] Figure 7 This is a schematic diagram of the structure of a material testing device provided in an embodiment of this application.

[0130] like Figure 7 As shown, the material testing apparatus 700 may include:

[0131] The control module 701 is used to control the target neutron source to emit original neutron beams into moderators of various thicknesses, so that the original neutron beams are slowed down by the moderators of various thicknesses to generate multiple neutron beams.

[0132] The acquisition module 702 is used to acquire the number of non-thermal neutrons and the total number of neutrons in the neutron beam;

[0133] The first determining module 703 is used to determine the number of thermal neutrons and the proportion of thermal neutrons corresponding to the neutron beam based on the number of non-thermal neutrons and the total number of neutrons.

[0134] The second determining module 704 is used to determine the neutron beam with the highest number of thermal neutrons and the neutron beam with the highest proportion of thermal neutrons from multiple neutron beams, and to determine the thickness of the moderator corresponding to the target neutron beam as the target thickness.

[0135] Test module 705 is used to perform thermal neutron shielding tests on target materials based on the target thickness of the target moderator, and to obtain the thermal neutron shielding rate corresponding to the target material.

[0136] The material testing device 700 described above is described in detail below:

[0137] In some embodiments, in order to obtain the number of non-thermal neutrons and the total number of neutrons in a neutron beam through experimental testing, the acquisition module 702 may specifically include:

[0138] The transmitting submodule is used to transmit a neutron beam to the target detector through the neutron beam exit port;

[0139] The first acquisition submodule is used to acquire the total number of neutrons detected by the target detector when no shielding is added to the neutron beam exit port.

[0140] The second acquisition submodule is used to acquire the number of non-thermal neutrons detected by the target detector when a cadmium sheet is added to the neutron beam exit port for shielding. The cadmium sheet is used to absorb thermal neutrons in the neutron beam.

[0141] In some embodiments, the first determining module 703 described above may specifically include:

[0142] The first determining submodule is used to determine the difference between the total number of neutrons and the number of non-thermal neutrons, and to use the difference as the number of thermal neutrons corresponding to the neutron beam.

[0143] The second determining submodule is used to determine the ratio between the number of thermal neutrons and the total number of neutrons, and to use the ratio as the proportion of thermal neutrons in the neutron beam.

[0144] In some embodiments, in order to determine the target neutron beam, the second determining module 704 described above may specifically include:

[0145] The third determination submodule is used to determine the product between the number of thermal neutrons and the percentage of thermal neutrons for each of the multiple neutron beams;

[0146] The fourth determination submodule is used to determine the neutron beam with the largest product value from multiple neutron beams as the target neutron beam.

[0147] In some embodiments, in order to obtain the thermal neutron shielding efficiency corresponding to the target material, the above-mentioned test module 705 may specifically include:

[0148] The control submodule is used to control the target neutron source to emit the original neutron beam into the target moderator with the target thickness, so that the original neutron beam is slowed down by the target moderator and then the target neutron beam is generated.

[0149] The testing submodule is used to perform thermal neutron shielding tests on target materials using the cadmium difference method and the target neutron beam to obtain the thermal neutron shielding rate corresponding to the target material.

[0150] In some embodiments, the above-mentioned test submodule may specifically include:

[0151] The transmitting unit is used to transmit the target neutron beam to the target detector through the neutron beam exit port;

[0152] The first acquisition unit is used to acquire the total number of neutrons detected by the target detector when no shielding is added to the neutron beam exit port.

[0153] The second acquisition unit is used to acquire the number of first non-thermal neutrons detected by the target detector when a cadmium sheet is added to the neutron beam exit port for shielding. The cadmium sheet is used to absorb thermal neutrons in the target neutron beam.

[0154] The third acquisition unit is used to acquire the total number of second neutrons detected by the target detector when the target material shielding is added to the neutron beam exit port.

[0155] The fourth acquisition unit is used to acquire the number of second non-thermal neutrons detected by the target detector when cadmium sheets and target materials are added to the neutron beam exit port at the same time.

[0156] The determining unit is used to determine the thermal neutron shielding rate of the target material based on the total number of first neutrons, the number of first non-thermal neutrons, the total number of second neutrons, and the number of second non-thermal neutrons.

[0157] Therefore, by controlling the target neutron source to emit raw neutron beams into moderators of varying thicknesses, multiple neutron beams are generated after each raw neutron beam is moderated by moderators of different thicknesses. The number of non-thermal neutrons and the total number of neutrons in these multiple neutron beams are obtained, and the number and percentage of thermal neutrons corresponding to each beam are determined. The neutron beam with the highest number and percentage of thermal neutrons is selected as the target neutron beam. After determining the target thickness based on the thickness of the moderator corresponding to the target neutron beam, thermal neutron shielding tests can be performed on the target material using the target moderator at that thickness. Thus, when testing the thermal neutron shielding performance of the target material, the degree of moderation of the moderator is determined. By using the target moderator to moderate the target neutron source, a target neutron beam with a higher number and percentage of thermal neutrons can be generated. This reduces relative error and improves the accuracy of the thermal neutron shielding performance test results for the target material.

[0158] Figure 8 This is a schematic diagram of the structure of an electronic device provided in an embodiment of this application.

[0159] The electronic device 800 may include a processor 801 and a memory 802 storing computer program instructions.

[0160] Specifically, the processor 801 may include a central processing unit (CPU), an application-specific integrated circuit (ASIC), or one or more integrated circuits that can be configured to implement the embodiments of this application.

[0161] Memory 802 may include mass storage for data or instructions. For example, and not limitingly, memory 802 may include a hard disk drive (HDD), floppy disk drive, flash memory, optical disk, magneto-optical disk, magnetic tape, or Universal Serial Bus (USB) drive, or a combination of two or more of these. Where appropriate, memory 802 may include removable or non-removable (or fixed) media. Where appropriate, memory 802 may be internal or external to the integrated gateway disaster recovery device. In a particular embodiment, memory 802 is non-volatile solid-state memory.

[0162] In certain embodiments, the memory may include read-only memory (ROM), random access memory (RAM), disk storage media devices, optical storage media devices, flash memory devices, and electrical, optical, or other physical / tangible memory storage devices. Thus, typically, memory includes one or more tangible (non-transitory) computer-readable storage media (e.g., memory devices) encoded with software including computer-executable instructions, and when the software is executed (e.g., by one or more processors), it is operable to perform the operations described with reference to the method according to one aspect of this application.

[0163] The processor 801 reads and executes computer program instructions stored in the memory 802 to implement any of the material testing methods in the above embodiments.

[0164] In some examples, the electronic device 800 may also include a communication interface 803 and a bus 810. For example, Figure 8 As shown, the processor 801, memory 802, and communication interface 803 are connected through bus 810 and complete communication with each other.

[0165] The communication interface 803 is mainly used to realize communication between various modules, devices, units and / or equipment in the embodiments of this application.

[0166] Bus 810 includes hardware, software, or both, that couples components of an online data traffic metering device together. For example, and not as a limitation, bus 810 may include an Accelerated Graphics Port (AGP) or other graphics bus, an Enhanced Industry Standard Architecture (EISA) bus, a Front Side Bus (FSB), HyperTransport (HT) interconnect, an Industry Standard Architecture (ISA) bus, an Infinite Bandwidth Interconnect, a Low Pin Count (LPC) bus, a memory bus, a Microchannel Architecture (MCA) bus, a Peripheral Component Interconnect (PCI) bus, a PCI-Express (PCI-X) bus, a Serial Advanced Technology Attachment (SATA) bus, a Video Electronics Standards Association Local (VLB) bus, or other suitable buses, or combinations of two or more of these. Where appropriate, bus 810 may include one or more buses. Although specific buses are described and illustrated in embodiments of this application, any suitable bus or interconnect is contemplated herein.

[0167] For example, the electronic device 800 can be a mobile phone, tablet computer, laptop computer, handheld computer, in-vehicle electronic device, ultra-mobile personal computer (UMPC), netbook, or personal digital assistant (PDA), etc.

[0168] The electronic device 800 can execute the material testing methods described in the embodiments of this application, thereby achieving the combination Figure 1 and Figure 7 The material testing methods and apparatus described.

[0169] Furthermore, in conjunction with the material testing methods in the above embodiments, this application embodiment can provide a computer-readable storage medium for implementation. This computer-readable storage medium stores computer program instructions; when these computer program instructions are executed by a processor, they implement any of the material testing methods in the above embodiments. Examples of computer-readable storage media include non-transitory computer-readable storage media, such as portable disks, hard disks, random access memory (RAM), read-only memory (ROM), erasable programmable read-only memory (EPROM or flash memory), portable compact disk read-only memory (CD-ROM), optical storage devices, magnetic storage devices, etc.

[0170] It should be clarified that this application is not limited to the specific configurations and processes described above and shown in the figures. For the sake of brevity, detailed descriptions of known methods are omitted here. In the above embodiments, several specific steps are described and shown as examples. However, the method process of this application is not limited to the specific steps described and shown. Those skilled in the art can make various changes, modifications, and additions, or change the order of steps, after understanding the spirit of this application.

[0171] The functional blocks shown in the above-described structural diagram can be implemented as hardware, software, firmware, or a combination thereof. When implemented in hardware, they can be, for example, electronic circuits, application-specific integrated circuits (ASICs), appropriate firmware, plug-ins, function cards, etc. When implemented in software, the elements of this application are programs or code segments used to perform the required tasks. Programs or code segments can be stored on a machine-readable medium or transmitted over a transmission medium or communication link via data signals carried on a carrier wave. "Machine-readable medium" can include any medium capable of storing or transmitting information. Examples of machine-readable media include electronic circuits, semiconductor memory devices, ROM, flash memory, erasable ROM (EROM), floppy disks, CD-ROMs, optical disks, hard disks, fiber optic media, radio frequency (RF) links, etc. Code segments can be downloaded via computer networks such as the Internet, intranets, etc.

[0172] It should also be noted that the exemplary embodiments mentioned in this application describe methods or systems based on a series of steps or apparatus. However, this application is not limited to the order of the above steps; that is, the steps can be performed in the order mentioned in the embodiments, or in a different order, or several steps can be performed simultaneously.

[0173] The aspects of this application have been described above with reference to flowchart illustrations and / or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of this application. It should be understood that each block in the flowchart illustrations and / or block diagrams, and combinations of blocks in the flowchart illustrations and / or block diagrams, can be implemented by computer program instructions. These computer program instructions can be provided to a processor of a general-purpose computer, a special-purpose computer, or other programmable data processing apparatus to produce a machine such that these instructions, executable via the processor of the computer or other programmable data processing apparatus, enable the implementation of the functions / actions specified in one or more blocks of the flowchart illustrations and / or block diagrams. Such a processor can be, but is not limited to, a general-purpose processor, a special-purpose processor, a special application processor, or a field-programmable logic circuit. It is also understood that each block in the block diagrams and / or flowcharts, and combinations of blocks in the block diagrams and / or flowcharts, can also be implemented by dedicated hardware performing the specified functions or actions, or can be implemented by a combination of dedicated hardware and computer instructions.

[0174] The above description is merely a specific implementation of this application. Those skilled in the art will clearly understand that, for the sake of convenience and brevity, the specific working processes of the systems, modules, and units described above can be referred to the corresponding processes in the foregoing method embodiments, and will not be repeated here. It should be understood that the protection scope of this application is not limited thereto. Any person skilled in the art can easily conceive of various equivalent modifications or substitutions within the technical scope disclosed in this application, and these modifications or substitutions should all be covered within the protection scope of this application.

Claims

1. A material testing method, characterized in that, include: The target neutron source is controlled to emit raw neutron beams into moderators of various thicknesses, so that the raw neutron beams are slowed down by the moderators of various thicknesses, thereby generating multiple neutron beams. Obtain the number of nonthermal neutrons and the total number of neutrons in the neutron beam; The number of thermal neutrons and the proportion of thermal neutrons corresponding to the neutron beam are determined based on the number of non-thermal neutrons and the total number of neutrons. From the plurality of neutron beams, the neutron beam with the highest number of thermal neutrons and the highest percentage of thermal neutrons is determined as the target neutron beam, and the thickness of the moderator corresponding to the target neutron beam is determined as the target thickness; Thermal neutron shielding test is performed on the target material based on the target modulator with the target thickness to obtain the thermal neutron shielding rate corresponding to the target material. Among the plurality of neutron beams, determining the neutron beam with the highest number of thermal neutrons and the highest percentage of thermal neutrons as the target neutron beam includes: For each of the plurality of neutron beams, determine the product between the number of thermal neutrons and the percentage of thermal neutrons; From the plurality of neutron beams, the neutron beam with the largest product value is determined as the target neutron beam.

2. The method according to claim 1, characterized in that, The process of obtaining the number of non-thermal neutrons and the total number of neutrons in the neutron beam includes: The neutron beam is emitted toward the target detector through the neutron beam exit port; Without adding any shielding to the neutron beam exit port, obtain the total number of neutrons detected by the target detector; With a cadmium sheet shielding added to the neutron beam exit port, the number of non-thermal neutrons detected by the target detector is obtained, wherein the cadmium sheet is used to absorb thermal neutrons in the neutron beam.

3. The method according to claim 1, characterized in that, The step of determining the number of thermal neutrons and the proportion of thermal neutrons corresponding to the neutron beam based on the number of non-thermal neutrons and the total number of neutrons includes: Determine the difference between the total number of neutrons and the number of non-thermal neutrons, and use the difference as the number of thermal neutrons corresponding to the neutron beam; Determine the ratio between the number of thermal neutrons and the total number of neutrons, and use the ratio as the percentage of thermal neutrons corresponding to the neutron beam.

4. The method according to claim 1, characterized in that, The thermal neutron shielding test of the target material by the target moderator based on the target thickness to obtain the thermal neutron shielding rate corresponding to the target material includes: The target neutron source is controlled to emit the original neutron beam toward the target moderator of the target thickness, so that the original neutron beam is slowed down by the target moderator and the target neutron beam is generated. Based on the cadmium difference method, the target material is subjected to thermal neutron shielding test using the target neutron beam to obtain the thermal neutron shielding rate corresponding to the target material.

5. The method according to claim 4, characterized in that, The method based on cadmium difference, which uses the target neutron beam to perform thermal neutron shielding tests on the target material to obtain the thermal neutron shielding rate corresponding to the target material, includes: The target neutron beam is emitted toward the target detector through the neutron beam exit port; Without adding any shielding to the neutron beam exit port, obtain the first total number of neutrons detected by the target detector; With a cadmium sheet shielding added to the neutron beam exit port, the number of the first non-thermal neutrons detected by the target detector is obtained, wherein the cadmium sheet is used to absorb thermal neutrons in the target neutron beam; With the target material shielding added to the neutron beam exit port, the total number of second neutrons detected by the target detector is obtained; With the cadmium sheet and the target material shielding added simultaneously at the neutron beam exit port, the number of second non-thermal neutrons detected by the target detector is obtained; The thermal neutron shielding rate of the target material is determined based on the first total number of neutrons, the first number of non-thermal neutrons, the second total number of neutrons, and the second number of non-thermal neutrons.

6. A material testing device, characterized in that, The device includes: The control module is used to control the target neutron source to emit raw neutron beams into moderators of various thicknesses, so that the raw neutron beams are slowed down by the moderators of various thicknesses to generate multiple neutron beams. The acquisition module is used to acquire the number of non-thermal neutrons and the total number of neutrons in the neutron beam; The first determining module is used to determine the number of thermal neutrons and the proportion of thermal neutrons corresponding to the neutron beam based on the number of non-thermal neutrons and the total number of neutrons. The second determining module is used to determine the neutron beam with the highest number of thermal neutrons and the neutron beam with the highest proportion of thermal neutrons from the plurality of neutron beams, and to determine the thickness of the moderator corresponding to the target neutron beam as the target thickness. The testing module is used to perform thermal neutron shielding tests on the target material based on the target modulator of the target thickness, and to obtain the thermal neutron shielding rate corresponding to the target material. The second determining module is also used for: For each of the plurality of neutron beams, determine the product between the number of thermal neutrons and the percentage of thermal neutrons; From the plurality of neutron beams, the neutron beam with the largest product value is determined as the target neutron beam.

7. An electronic device, characterized in that, The device includes: a processor and a memory storing computer program instructions; When the processor executes the computer program instructions, it implements the steps of the material testing method as described in any one of claims 1-5.

8. A computer-readable storage medium, characterized in that, The computer-readable storage medium stores computer program instructions that, when executed by a processor, implement the steps of the material testing method as described in any one of claims 1-5.

9. A computer program product, characterized in that, When the instructions in the computer program product are executed by the processor of the electronic device, the electronic device causes the electronic device to perform the steps of the material testing method as described in any one of claims 1-5.

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