阅读说明：本技术 一种中子辐射屏蔽结构及其制成的屏蔽装置、检测方法 (Neutron radiation shielding structure, shielding device manufactured by same and detection method ) 是由 徐佳梁 田清 姜亮亮 周美玲 于 2021-08-23 设计创作，主要内容包括：本发明提供了一种中子辐射屏蔽结构及其制成的屏蔽装置、检测方法,其中该中子辐射屏蔽结构包括：基体,悬挑,其中所述悬挑在所述基体上柱立,并呈阵列布设状。籍此减少反照中子数量,从而有效提升中子屏蔽效果。(The invention provides a neutron radiation shielding structure, a shielding device made of the neutron radiation shielding structure and a detection method of the neutron radiation shielding structure, wherein the neutron radiation shielding structure comprises: the cantilever is arranged on the substrate in a column standing manner and is in an array arrangement shape. Therefore, the quantity of the back-illuminated neutrons is reduced, and the neutron shielding effect is effectively improved.)

1. A neutron radiation shielding structure, comprising: the cantilever is arranged on the substrate, stands on the substrate and is distributed in an array shape.

2. The neutron radiation shielding structure of claim 1, wherein the overhang has a hexahedral shape.

3. The neutron radiation shielding structure of claim 1, wherein the overhang is at least one of a cuboid, a cube.

4. The neutron radiation shielding structure of claim 1, wherein the overhangs are cruciform in shape and arranged in an array to meet to form a waffle.

5. The neutron radiation shielding structure of claim 1, wherein the array spacing of the overhangs on the substrate is less than or equal to 5 cm.

6. The neutron radiation shielding structure of claim 1, wherein a junction surface of the base and the overhang is planar.

7. The neutron radiation shielding structure of claim 1, wherein at least one of the matrix and the overhangs is made of concrete including portland cement.

8. The neutron radiation shielding structure of claim 1, wherein the overhangs are arranged perpendicular to the matrix array.

9. A neutron radiation shield, comprising: the shielding surface, wherein the shielding surface is made of the neutron radiation shielding structure of any of claims 1 to 9.

10. A method of neutron radiation shield detection, comprising the steps of: establishing a spherical detection system, arranging a detector at the positive hemisphere position of the X axis of the system, placing the neutron shielding structure of any one of claims 1 to 9 at the origin of the system, enabling the center of the matrix to coincide with the origin of coordinates of the system, and enabling the connection surface of the matrix and the cantilever to coincide with the YOZ surface of the system; the neutron source is arranged on the X axis and is incident to the position of the system origin so that the detector can read detection data.

Technical Field

The invention relates to a neutron radiation shielding technology, in particular to a neutron radiation shielding structure, a shielding device made of the neutron radiation shielding structure and a detection method.

Background

With the rapid development of industries such as nuclear energy, irradiation processing, nondestructive testing, radiation therapy and the like, high-energy rays are widely used in various fields such as industry, medical treatment, scientific research and the like. Common high-energy rays include X-rays, gamma rays, neutron rays and the like, so the problems of irradiation and protection of the high-energy rays are always the focus of attention.

Wherein, the neutron has strong penetrating power when passing through the material, and the danger to the human body is more serious than the X-ray and the gamma ray with the same dosage. After a human body is irradiated by neutrons, intestines and stomach and male gonads can be seriously damaged, the biological effect of tumor induction is high, early death is easily caused, the damaged organism is easily infected and has high degree, and the relative biological effect of the opacity of the eye crystal is 2-14 times of that of gamma or X rays. It is very likely to cause hematopoietic organ failure, digestive system injury, and central nerve injury. It can also cause malignant tumor, leukemia, cataract, etc. Neutron irradiation also produces genetic effects that affect the development of offspring in the irradiated.

Therefore, the neutron shielding protection is particularly important for the safety of workers in actual work.

At present, the existing neutron shielding technology generally focuses on the research on shielding materials, for example, the traditional neutron shielding material mainly uses boron-based or lead-based polyethylene composite shielding materials as main bodies, and the concrete shielding surface of the neutron shielding device made of the shielding materials is also mostly in a plate or sheet structure.

The inventor considers another approach for this purpose, and attempts to improve the structure of the shielding surface made of the existing shielding material to further supplement and improve the neutron shielding effect.

Disclosure of Invention

The invention mainly aims to provide a neutron radiation shielding structure, a shielding device made of the neutron radiation shielding structure and a detection method of the neutron radiation shielding structure, so as to achieve the aims of the inventor in the background art.

In order to achieve the above object, according to a first aspect of the present invention, there is provided a neutron radiation shielding structure including: the cantilever is arranged on the substrate, stands on the substrate and is distributed in an array shape.

Further, in a possible preferred embodiment, the overhang has a hexahedral shape.

Further, in a possible preferred embodiment, the overhang is at least one of a rectangular parallelepiped and a cube.

Further, in a possible preferred embodiment, the cantilever has a polygonal shape.

Further, in a possible preferred embodiment, the overhangs are in the shape of a cross and are arranged in an array to form a waffle.

Further, in a possible preferred embodiment, the array pitch of the overhangs on the substrate is less than or equal to 5 cm.

Further, in a possible preferred embodiment, the connection surface between the base body and the overhang is a plane.

Further, in a possible preferred embodiment, at least one of the base and the overhang is made of concrete comprising portland cement.

Further, in a possible preferred embodiment, the overhangs are arranged perpendicular to the matrix array.

In order to achieve the above object, according to a second aspect of the present invention, there is also provided a neutron radiation shielding detection method, including the steps of: establishing a spherical detection system, arranging a detector at the positive hemisphere position of the X axis of the system, placing any neutron shielding structure at the origin of the system, enabling the center of the matrix to coincide with the origin of coordinates of the system, and enabling the connection surface of the matrix and the cantilever to coincide with the YOZ surface of the system; the neutron source is arranged on the X axis and is incident to the position of the system origin so that the detector can read detection data.

In order to achieve the above object, according to a third aspect of the present invention, there is also provided a neutron radiation shielding apparatus comprising: a shielding surface, wherein the shielding surface is made of the neutron radiation shielding structure.

Compared with the shielding surface structure in the prior art, the neutron radiation shielding structure, the shielding device manufactured by the neutron radiation shielding structure and the detection method provided by the invention can obviously reduce the quantity of the albedo neutrons, thereby effectively improving the neutron shielding effect, have low implementation cost, are suitable for improving the prior art, are beneficial to technical popularization, and can stay for a longer time in a radiation operation area for workers for inspection and maintenance in actual use, thereby effectively helping the whole operation planning.

Drawings

The accompanying drawings, which are incorporated in and constitute a part of this application, illustrate embodiments of the invention and, together with the description, serve to explain the invention and not to limit the invention. In the drawings:

fig. 1 is a schematic structural view of a neutron radiation shielding structure according to a first embodiment of the present invention;

FIG. 2 is the spatial distribution of albedo neutrons of Table 1 of a first embodiment of the present invention;

FIG. 3 is the albedo neutron energy distribution plot of Table 2 for a first embodiment of the present invention;

FIG. 4 is a schematic diagram of the array arrangement of the regular hexagonal cantilevers on the substrate according to the first embodiment of the present invention;

FIG. 5 is a schematic view of a second embodiment of the invention showing a cruciform overhang placed on a substrate;

FIG. 6 is a schematic view of a second embodiment of the present invention showing a cross-shaped cantilever wafer structure arranged on a substrate;

FIG. 7 is a table 3 spatial distribution data plot of a second embodiment of the present invention;

FIG. 8 is a table 4 energy distribution data plot of a second embodiment of the present invention;

FIG. 9 is a data diagram of a second embodiment of the invention of an isotropic neutron source detection waffle structure;

FIG. 10 is a diagram of a neutron shield detection system according to a third embodiment of the present invention;

FIG. 11 is a diagram of a neutron shield detection system according to a third embodiment of the invention.

Detailed Description

The following describes in detail embodiments of the present invention. The following examples will assist those skilled in the art in further understanding the invention, but are not intended to limit the invention in any way. It should be noted that variations and modifications can be made by persons skilled in the art without departing from the spirit of the invention. All falling within the scope of the present invention. Furthermore, the embodiments and features of the embodiments may be combined with each other in the present application without conflict.

In order to make those skilled in the art better understand the technical solution of the present invention, the technical solution in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be obtained by a person skilled in the art without any inventive step based on the embodiments of the present invention, shall fall within the scope of the present invention. Furthermore, the terms "comprising" and "having," as well as any variations thereof, are intended to cover non-exclusive inclusions.

(A)

Referring to fig. 1 to 4, the neutron radiation shielding structure provided by the present invention includes: the cantilever is arranged on the substrate, stands on the substrate and is distributed in an array shape. Wherein the overhang may alternatively be a hexahedral rectangle, as shown in fig. 1. In yet other alternative embodiments, a regular hexahedral shape may be used.

The base body can be a plane shielding wall scheme in the prior art, and the cantilever can be arranged on the plane shielding wall in the prior art according to the scheme of the embodiment so as to form the improvement on the prior art, and still the scheme which is superior to the scheme of independently arranging the prior plane shielding wall in the aspect of reducing the quantity of the reflection neutrons can be realized.

In addition, the material used for the cantilever is not limited in this embodiment, and in the experimental example of this embodiment, portland cement concrete is preferably used, but it should be understood by those skilled in the art that in other possible alternative embodiments, other materials for increasing the neutron shielding performance may be used instead, and therefore any solution that improves the cantilever only by material replacement is within the disclosure of this embodiment.

Experimental example 1

To prove the effectiveness of the neutron radiation shielding structure proposed in this embodiment, this embodiment was experimented with the following parameters.

Matrix: adopting a plane shielding wall body with the size of 100x100x35 cm

And (3) cantilever: using a regular hexahedron with a size of 5x5x10 cm

Regular hexahedron angle: vertical wall arrangement

Arrangement density: 10x10cm

The spacing distance is as follows: 5cm above and below

Preparing materials: the base body and the cantilever adopt Portland cement concrete

Comparison object: plane shielding wall

Experimental data and analysis for the regular hexahedral structure are as follows:

TABLE 1 spatial distribution data (100 eV) TABLE 2 energy distribution data (100 eV)

According to the experimental results, the following results are obtained:

1) the quantity of the albedo neutrons that the shield wall of structure of encorbelmenting of installing additional produced is showing and is reducing:

as shown in fig. 4, the array structure of the regular hexahedral structure overhanging the substrate is shown, and as can be seen from the output data of table 1 or table 2, the total number of the albedo neutrons is reduced from 64.73% to 55.94%, and the total reduction is 8.79%.

2) Wherein the neutron number in the middle and high latitude areas (30-90 degrees) is obviously reduced, and the neutron number in the bottom latitude area (0-30 degrees) is slightly increased:

from the data in table 1, a spatial distribution map 2 of the albedo neutrons can be plotted. The neutron quantity in a medium and high latitude area (30-90 degrees) is obviously reduced, and the neutron quantity in a bottom latitude area (0-30 degrees) is slightly increased.

3) The neutron count in the high energy region is significantly reduced and the neutron count in the low energy region is slightly increased:

the data in table 2 can be used to plot a albedo neutron energy distribution 3, which shows that the number of neutrons in the high energy region is significantly reduced and the number of neutrons in the low energy region is slightly increased.

According to the experimental result data, the neutron radiation shielding structure provided by the embodiment can obviously reduce the quantity of the albedo neutrons, so that the neutron shielding effect is better than that of a planar shielding wall.

(II)

Referring to fig. 5 to 8, in another preferred embodiment, the neutron radiation shielding structure provided by the present invention includes: the cantilever is arranged on the substrate, stands on the substrate and is distributed in an array shape. As shown in FIG. 5, the overhangs may alternatively be cross-shaped, and each cross-shaped overhang may be spaced apart and perpendicular to the substrate.

It should be noted that, if the cross-shaped overhangs are arranged in an end-to-end array as shown in fig. 6 to form a wafer shape, the solution is better than the first embodiment and the present embodiment, in which the overhangs are arranged at intervals in a cross shape.

Specifically, fig. 4 is a cross section of a regular hexahedral structure in the x =5 plane, and fig. 6 is a cross section of a waffle structure in the x =5 plane. The structure of this example and the structure of the second experimental example are changed from the regular hexahedron of fig. 4 to the structure of "waffle" of fig. 6, that is, the material is extended along the y-axis and the z-axis until the material is communicated with the adjacent overhanging structure. Therefore, in the following second experimental example, the data test comparison is performed by taking the cubic structure of fig. 4 and the wafer structure of fig. 6 as an example.

In addition, the design concept of the waffle structure is that the inventor accidentally finds out through experiments that after the trend that the volume of the overhanging structure is proportional to the restraining force of the reflection neutrons, the volume of the overhanging structure is increased as much as possible on the basis of a regular hexahedron, and a derived product is obtained.

On the other hand, in the embodiment, the base body can be a planar shielding wall scheme in the prior art, and the cantilever can be arranged on the planar shielding wall in the prior art according to the scheme in the embodiment, so that the improvement of the prior art is formed, and the improvement of the scheme in reducing the number of reflection neutrons in comparison with the scheme of independently arranging the prior planar shielding wall can still be realized.

Meanwhile, the preparation material used for the cantilever is not limited in this embodiment, and in the experimental example of this embodiment, portland cement concrete is preferably used for the preparation, but it should be understood by those skilled in the art that in other possible alternative embodiments, other materials for increasing the neutron shielding performance may be used instead, and therefore any solution that improves the cantilever only in a material alternative manner is within the disclosure scope of this embodiment.

Experimental example 2

To prove the effectiveness of the neutron radiation shielding structure proposed in this embodiment, this embodiment was experimented with the following parameters.

In the present embodiment, the structure of the waffle, which is derived from a regular hexahedral structure, can be composed of a plurality of small crosses, each 5cm thick and 10cm high, placed in the middle of a single 10 × 10cm cell. The experimental material was still portland cement concrete.

Experimental data and analysis of wafer structure were as follows:

angle of rotation	Plane wall	Regular hexahedron	Waffle structure
				0	0.000E+00	0.000E+00	0.000E+00
10	1.987E-02	2.265E-02	1.859E-02
				20	5.709E-02	6.311E-02	4.425E-02
30	8.717E-02	8.805E-02	5.191E-02
				40	1.078E-01	9.738E-02	5.459E-02
50	1.121E-01	9.616E-02	5.111E-02
				60	1.033E-01	7.876E-02	4.169E-02
70	8.111E-02	5.478E-02	2.882E-02
				80	5.031E-02	2.954E-02	1.552E-02
90	1.593E-02	9.533E-03	4.257E-03
				100	0.000E+00	4.702E-04	1.549E-05
Total of	6.348E-01	5.404E-01	3.108E-01

TABLE 3 spatial distribution data sheet (1 eV)

(Energy)	Plane wall	Regular hexahedron	Waffle structure
				0.000E+00	0.000E+00	0.000E+00	0.000E+00
1.00E-07	3.024E-01	3.232E-01	2.317E-01
				2.00E-07	1.018E-01	8.358E-02	4.337E-02
3.00E-07	4.265E-02	2.891E-02	9.443E-03
				4.00E-07	2.900E-02	1.818E-02	5.370E-03
5.00E-07	2.132E-02	1.369E-02	4.003E-03
				6.00E-07	1.810E-02	1.160E-02	3.334E-03
7.00E-07	2.156E-02	1.341E-02	3.646E-03
				8.00E-07	3.459E-02	1.910E-02	4.477E-03
9.00E-07	3.946E-02	1.874E-02	3.636E-03
				1.00E-06	2.034E-02	8.550E-03	1.445E-03
1.10E-06	3.322E-03	1.367E-03	2.172E-04
				1.20E-06	1.481E-04	5.757E-05	0.000E+00
Total of	6.348E-01	5.404E-01	3.108E-01

TABLE 4 quantity distribution data sheet (1 eV)

Taking the spatial distribution data table (1 eV) in table 3, the energy distribution data table (1 eV) in fig. 7, the energy distribution data table (1 eV) in table 4, and the energy distribution data table (8), taking the neutron source as an example, the numbers of the albedo neutrons generated by the plane shielding wall, the regular hexahedron, and the waffle structure are 63.48%, 54.04%, and 31.08%, respectively, in the case of the 1eV neutron incident shielding body, the regular hexahedron cantilever structure reduces 9.44% of the albedo neutrons, and the waffle cantilever structure reduces 32.4% of the albedo neutrons, compared with the shielding wall without the cantilever structure.

It can be seen that according to the above experimental results, the waffle structure in the second embodiment has a significant improvement in reducing the key parameters of the quantity of the albedo neutrons compared with the regular hexahedral structure in the second embodiment 1, and the sub-shielding effect is better.

In addition, the inventor also makes corresponding verification in order to prove that the waffle structure can be applied to more complicated use scenarios (such as an isotropic neutron source) and whether the waffle structure is still effective.

If two neutron beams are respectively used for irradiating the surfaces of the convex part and the concave part of the waffle structure, and compared with a common plane, as shown in fig. 9, a first curve a1, a second curve a2 and a third curve A3 are respectively incident on the concave part, the convex part and the common plane of the waffle structure, the area formed by the curves and the x axis in the graph represents the number of generated anti-neutrons, the area of the curve a2 is 5.95% larger than that of the blue curve, the area of the curve a1 is 32.4% smaller than that of the curve A3, and the total attenuation caused by the incident concave part is much larger than the gain caused by the incident convex part.

The isotropic neutron source can be decomposed and simplified into a plurality of single-beam neutron sources, so that under the condition of a more complex neutron source, the waffle structure can still achieve an ideal effect of reducing the quantity of the anti-neutron.

In addition, it should be noted that, according to the first and second embodiments, the scheme of adding the cantilever on the planar shielding wall can effectively reduce the number of the albedo neutrons and improve the neutron shielding effect. However, although the overhanging structure is exemplified by the hexahedron and the cross shape in this embodiment, the shape of the overhanging structure is not limited, and those skilled in the art can fully adopt overhanging structures with other shapes and structures to be arranged on the substrate according to the concept of the present invention to meet the requirements of different neutron shielding effects, so that any alternative implementation manner of the overhanging shape is within the scope of the present invention.

On the other hand, according to the above-mentioned embodiment of the present invention, the array structure of the overhangs on the substrate does not need to have complete spacing between overhangs, so the above-mentioned expression of the array layout of the present invention includes the idea that the overhangs can have complete spacing (e.g. hexagonal structure) or at least partial connection (wafer structure),

on the other hand, although the substrate is exemplified by a plane in the above embodiments, in other possible alternative embodiments, the substrate may also be a curved surface structure to meet the structural requirements of the shielding scene, so that no matter what kind of variation structure is adopted for the substrate, it is within the scope of the disclosure of the present invention as long as the overhangs can be arranged thereon in an array and protrude from the surface of the substrate.

(III)

In a third aspect of the present invention, a neutron radiation shielding detection method is further provided, including the steps of: establishing a spherical detection system, arranging a detector at the positive hemisphere position of the X axis of the system, placing the neutron shielding structure in the embodiment at the origin of the system, enabling the center of the matrix to coincide with the origin of coordinates of the system, and enabling the connection surface of the matrix and the cantilever to coincide with the YOZ surface of the system; the neutron source is arranged on the X axis (such as 40,0, 0) to be incident (such as 0,0, 0) to the system origin position, so that the detector can read detection data.

Wherein the neutron source used for detection preferably comprises: low-energy neutrons, 1eV and 100eV, are incident at the origin in the form of a beam of neutrons.

Specifically, the experimental results of the first and second embodiments show that the cantilever scheme of the present invention can affect the albedo neutrons generated in the system in three levels:

1) the effect of the total neutron count is negated. The quantity of the albedo neutrons generated by the shielding wall is reduced;

2) reflecting the influence of the spatial distribution of neutrons. The number of neutrons in a medium and high latitude area (30-90 degrees) is obviously reduced, and the number of neutrons in a bottom latitude area (0-30 degrees) is slightly increased;

3) reflecting the influence of the neutron energy distribution. The number of neutrons in the high energy region is significantly reduced and the number of neutrons in the low energy region is slightly increased.

To help understand the 2 nd effect, as shown in fig. 10, the neutron shielding detection system is illustrated, the whole detection system is a sphere, the X-axis forward hemisphere is provided as a detector, the hexahedron is a position schematic of a shielding wall, the center of the shielding wall coincides with the center of the coordinate axis, and the cantilever structure is also directly applied to the surface, which also coincides with the YOZ surface. While the neutron source is located on the X-axis (40, 0, 0), the simulated neutron source has both 1eV and 100eV initial energies, incident as a beam of neutrons at the origin location (0, 0, 0).

As shown in fig. 11, number 1 is the position of the shield; number 2 is the position of the incident neutron source; the sphere located in the positive direction of the x-axis is the detector. The neutron sources used in the simulation are mainly low-energy neutrons (1 eV and 100 eV), and the neutron sources in the simulation experiment are positioned on the coordinate axes (40, 0 and 0). Thereby effectively realizing the detection of the neutron radiation shield.

(IV)

In a fourth aspect of the present invention, there is also provided a neutron radiation shielding apparatus, including: a shielding surface, wherein the shielding surface is made of the neutron radiation shielding structure in any one of the above embodiments.

In summary, compared with the shielding surface structure in the prior art, the neutron radiation shielding structure, the shielding device manufactured by the neutron radiation shielding structure and the detection method provided by the invention can obviously reduce the number of the albedo neutrons, thereby effectively improving the neutron shielding effect, have low implementation cost, are suitable for improving the prior art, are beneficial to technical popularization, and in practical use, for workers for inspection and maintenance, the neutron radiation shielding structure can stay in a radiation operation area for a longer time, thereby effectively helping the whole operation plan.

The preferred embodiments of the invention disclosed above are intended to be illustrative only. The preferred embodiments are not intended to be exhaustive or to limit the invention to the precise embodiments disclosed. Obviously, many modifications and variations are possible in light of the above teaching. The embodiments were chosen and described in order to best explain the principles of the invention and the practical application, to thereby enable others skilled in the art to best utilize the invention. The invention is limited only by the claims and the full scope and equivalents thereof, and any modification, equivalent replacement, or improvement made within the spirit and principle of the invention should be included in the protection scope of the invention.

It will be appreciated by those skilled in the art that, in addition to implementing the system, apparatus and various modules thereof provided by the present invention in the form of pure computer readable program code, the same procedures may be implemented entirely by logically programming method steps such that the system, apparatus and various modules thereof provided by the present invention are implemented in the form of logic gates, switches, application specific integrated circuits, programmable logic controllers, embedded microcontrollers and the like. Therefore, the system, the device and the modules thereof provided by the present invention can be considered as a hardware component, and the modules included in the system, the device and the modules thereof for implementing various programs can also be considered as structures in the hardware component; modules for performing various functions may also be considered to be both software programs for performing the methods and structures within hardware components.

In addition, all or part of the steps of the method according to the above embodiments may be implemented by a program instructing related hardware, where the program is stored in a storage medium and includes several instructions to enable a single chip, a chip, or a processor (processor) to execute all or part of the steps of the method according to the embodiments of the present application. And the aforementioned storage medium includes: a U-disk, a removable hard disk, a Read-Only Memory (ROM), a Random Access Memory (RAM), a magnetic disk or an optical disk, and other various media capable of storing program codes.

In addition, any combination of various different implementation manners of the embodiments of the present invention is also possible, and the embodiments of the present invention should be considered as disclosed in the embodiments of the present invention as long as the combination does not depart from the spirit of the embodiments of the present invention.