KR20210090411A - A neutron shielding maetrial and a method for manufacturing the same - Google Patents

Abstract

An embodiment of the present invention provides a neutron shielding material and a method for manufacturing the same. The method for manufacturing a neutron shielding material comprises the steps of: (a) preparing a metal base material; (b) supplying metal powder and ceramic powder to at least a portion of the upper surface of the metal base material; (c) melting the metal powder and the ceramic powder by irradiating a laser; and (d) solidifying a product from the step (c) to form a cermet layer, wherein the steps (b) to (d) are performed one or more times to prepare a material having a predetermined shape. Therefore, in manufacturing a spent nuclear fuel dry storage container using the material according to an aspect of the present invention, it is possible to reduce the separation between shielding bodies.

Description

Sculpture for neutron shielding and method for manufacturing the same {A NEUTRON SHIELDING MAETRIAL AND A METHOD FOR MANUFACTURING THE SAME}

The present invention relates to a neutron shielding sculpture and a method for manufacturing the same, and more particularly, to a method for manufacturing a neutron shielding sculpture using three-dimensional printing (3D printing) or additive manufacturing (AM) technology. it's about

Recently, a neutron shield made of a neutron shielding material is mainly used when manufacturing a dry storage container for spent nuclear fuel. The neutron shield is installed in a form surrounding the nuclear fuel assembly inside the dry storage container, and is used to control the criticality of nuclear fuel.

US Patent Application Publication No. US2007/0064860 discloses an invention related to an aluminum-based neutron absorber and a method for manufacturing the same. According to the manufacturing method, the ceramic (B ₄ C) powder and the metal (Al) powder are homogeneously mixed through a milling method, and then the mixed powder is put into a mold made of aluminum (Al) or stainless steel and heating is performed. do. Subsequently, a box-shaped neutron absorber is transformed into a plate-shaped neutron absorber through a rolling process, and is used to manufacture a spent nuclear fuel dry storage container.

However, according to the manufacturing method disclosed in the US Patent Application Publication No. US2007/0064860, there is a limitation in manufacturing the neutron absorber of various shapes, and there is a problem that the separation between the absorbers is easily generated when the structure is manufactured using the neutron absorber. . In particular, when welding technology is applied to the joining of structures, there is a high possibility that the distribution of the neutron absorber is changed or deformation due to welding defects or distortion occurs.

The present invention is to solve the problems of the prior art described above, and an object of the present invention is to manufacture a neutron shielding sculpture of various shapes that could not be implemented in the prior art, so that the shielding body of a complex shape required in devices or parts in which the shielding body is used is produced. manufacturing is possible. It is also possible to provide a method for manufacturing a neutron shielding sculpture capable of reducing the separation between shielding bodies when manufacturing a spent nuclear fuel dry storage container by applying the three-dimensional additive manufacturing technology according to an aspect of the present invention.

In addition, another object of the present invention is to produce a cermet sculpture through an additive manufacturing method, thereby harmoniously realizing not only the high-strength properties of ceramic but also the excellent electrical and thermal conductivity of metals, such as electrical work materials, processing equipment, automobile engine friction parts, munitions, etc. It is to provide an applicable cermet sculpture.

One aspect of the present invention comprises the steps of (a) preparing a metal base material; (b) supplying a metal powder and a ceramic powder to at least a portion of the upper surface of the metal base material; (c) melting the metal powder and the ceramic powder by irradiating a laser; And (d) solidifying the product of step (c) to form a cermet layer; including, wherein steps (b) to (d) are performed one or more times to prepare a sculpture having a predetermined shape, It is possible to provide a method for manufacturing a sculpture for neutron shielding.

In one embodiment, the step (b) and the step (c) may be performed simultaneously.

In one embodiment, the step (c) may be performed at a temperature lower than the melting point of the metal base material and higher than the melting point of the metal powder.

In one embodiment, (e) cutting the neutron shielding sculpture by a predetermined height and separating it from the metal base material; may further include.

In one embodiment, the metal base material is made of aluminum (Al), titanium (Ti), nickel (Ni), chromium (Cr), iron (Fe), stainless steel, tungsten (W), and a combination of two or more thereof. It may include one selected from the group.

In an embodiment, the metal powder may include one selected from the group consisting of aluminum (Al), iron (Fe), stainless steel, copper (Cu), tungsten (W), and a mixture of two or more thereof.

In one embodiment, the ceramic powder is boron carbide (Boron carbide), boron oxide (Boron oxide), boron nitride (Boron nitride), cadmium carbide (Cadmium carbide), cadmium oxide (Cadmium oxide), cadmium nitride ( Cadmium nitride), indium carbide (Indium carbide), indium oxide (Indium oxide), indium nitride (Indium nitride), samarium carbide (Samarium carbide), samarium oxide (Samarium oxide), samarium nitride (Samarium nitride), hafnium carbide (Hafnium carbide), hafnium oxide (Hafnium oxide), hafnium nitride (Hafnium nitride), europium carbide (Europium carbide), europium oxide (Europium oxide), europium nitride (Europium nitride), gadolinium carbide (Gadolinium carbide) ), gadolinium oxide (Gadolinium oxide), gadolinium nitride (Gadolinium nitride), and may include one selected from the group consisting of a mixture of two or more thereof.

In one embodiment, the ceramic content of the neutron shielding sculpture may be 5 to 50% by weight based on the total weight of the neutron shielding sculpture.

Another aspect of the present invention may provide a neutron shielding sculpture manufactured by the above-described method.

According to one aspect of the present invention, by three-dimensional lamination manufacturing of neutron shielding sculptures of various shapes that could not be implemented in the prior art, it is possible to manufacture a shielding body having a complex shape required for a device or component in which the shielding body is used. When manufacturing a spent nuclear fuel dry storage container using the sculpture according to an aspect of the present invention, it is possible to reduce the separation between the shielding bodies.

In addition, according to an aspect of the present invention, by manufacturing the cermet sculpture through the additive manufacturing method, the high-strength properties of ceramics as well as the excellent electrical and thermal conductivity of metals are harmoniously implemented to provide electrical work materials, processing equipment, automobile engine friction parts, It is possible to implement a cermet sculpture applicable to munitions and the like.

The effects of the present invention are not limited to the above effects, but it should be understood to include all effects that can be inferred from the configuration of the invention described in the detailed description or claims of the present invention.

1 shows the structure of a neutron shielding sculpture according to an embodiment of the present invention formed on a metal base material.
2 is an image of a cross-section of a neutron shielding sculpture according to an embodiment of the present invention taken with a metal microscope.
3 is an SEM image of a crack (macro crack) generated inside a specimen for neutron shielding according to a comparative example of the present invention.
4 and 5 are images taken with a metal microscope and SEM images of micro cracks generated inside the specimen for neutron shielding according to a comparative example of the present invention, respectively.
6 shows the results of thermal expansion analysis using COMSOL MULTIPHYSICS based on the results of photographing the specimen for neutron shielding according to an embodiment of the present invention.
7 and 8 are images taken with a metal microscope and SEM images of micro cracks generated inside the specimen for neutron shielding according to an embodiment of the present invention, respectively.
9 shows the thickness of the mixed layer (cutting depth) with respect to the accumulated heat (total heat input) of the neutron shielding sculpture according to an embodiment of the present invention.
Figure 10 shows the XRD (X-Ray Diffraction) analysis results of the neutron shielding sculpture according to a comparative example of the present invention.
11 shows the XRD analysis result of the neutron shielding sculpture according to an embodiment of the present invention.
12 is an image of a cut portion and an upper portion of a specimen for neutron shielding according to an embodiment of the present invention.
13 is an image of a region where a boundary melting phenomenon occurs in the process of manufacturing a cylindrical neutron shielding sculpture according to an embodiment of the present invention.

Hereinafter, the present invention will be described with reference to the accompanying drawings. However, the present invention may be embodied in several different forms, and thus is not limited to the embodiments described herein. And in order to clearly explain the present invention in the drawings, parts irrelevant to the description are omitted, and similar reference numerals are attached to similar parts throughout the specification.

Throughout the specification, when a part is "connected" with another part, this includes not only the case where it is "directly connected" but also the case where it is "indirectly connected" with another member interposed therebetween. . In addition, when a part "includes" a certain component, this means that other components may be further provided without excluding other components unless otherwise stated.

When a range of numerical values is recited herein, the values have the precision of the significant figures provided in accordance with the standard rules in chemistry for significant figures, unless the specific range is otherwise stated. For example, 10 includes the range of 5.0 to 14.9 and the number 10.0 includes the range of 9.50 to 10.49.

As used herein, the term “additive manufacturing (AM)” refers to a method of manufacturing a sculpture by connecting materials based on 3D shape data. For example, it refers to a method of manufacturing a sculpture by forming layers layer by layer.

As used herein, the term "Direct Energy Deposition (DED)" refers to an additive manufacturing method in which a material is melted using thermal energy to form a layer by layer. While the DED method has lower precision compared to the PBF (Powder Bed Fusion) method, it is largely distinguished in terms of high productivity and easy repeatability without size restrictions. In addition, according to the DED method, it is possible to manufacture a sculpture having high strength and impact value.

As used herein, the term “cermet” refers to a composite material composed of a ceramic and a metal.

As used herein, the term “total heat input” is calculated as in Equation 1 below.

[Equation 1]

Total heat input[J] = Specific Energy[J/mm ² ] * Heating Area[mm ² ] * number of layer

In Equation 1, the specific energy (Specific Energy) means the amount of energy applied per unit area of the base material, the heating area (Heating Area) means the area of the base material heated by the heat source, the number of layers (number) of layer) means the number of layers that are stacked to form a neutron shielding sculpture.

Manufacturing method for neutron shielding sculpture

1 shows the structure of a neutron shielding sculpture according to an embodiment of the present invention formed on a metal base material.

According to the manufacturing method of the neutron shielding sculpture according to an aspect of the present invention, (a) preparing a metal base material; (b) supplying a metal powder and a ceramic powder to at least a portion of the upper surface of the metal base material; (c) melting the metal powder and the ceramic powder by irradiating a laser; and (d) solidifying the product of step (c) to form a cermet layer; including, wherein steps (b) to (d) are performed one or more times to prepare a sculpture having a predetermined shape have.

The present invention relates to a method of manufacturing a neutron shielding sculpture using a three-dimensional printer, which is one of the core technologies of the 4th industrial revolution. In the present invention, unlike the prior art, since the material of the shielding body is supplied through an independent supply device, the productivity of the shielding body can be improved by omitting the milling method. In addition, since the material is melted at the same time as the powder supply to form a shield, it is possible to simplify the conventional mixing process and heating process sequentially in one step.

As a non-limiting example of the present invention, the sculpture having the "predetermined shape" may be a prism or a cylinder for accommodating spent nuclear fuel, but is not particularly limited thereto. The sculpture having the predetermined shape may be processed into a form that can be easily carried out by a person skilled in the art in storing the spent nuclear fuel.

In the case of manufacturing a cermet according to the extrusion method, which is a conventional manufacturing technique, unlike an elastic body such as rubber, due to the essential characteristics of a cermet with high hardness, the neutron shielding body was extruded into a plate shape, then cut and joined to process it. Since the present invention can easily manufacture various types of neutron shielding bodies by changing three-dimensional shape data, it is possible to innovatively change the shape of the shielding body, which was considered a limitation of the prior art, and complex required for devices or parts in which the shielding body is used. It is possible to manufacture a shaped shielding body. In addition, it is possible to solve the separation problem that occurs when manufacturing the shield structure of the spent nuclear fuel storage container.

The method for manufacturing the neutron shielding sculpture may further include (e) cutting the neutron shielding sculpture by a predetermined height and separating it from the metal base material.

As a non-limiting example of the present invention, the "predetermined height" may be calculated as in Equation 2 below if the amount of accumulated heat is less than 200,000 J.

[Equation 2]

X/X ₀ = 0.0003 * Y/Y ₀ + 10.291

As a non-limiting example of the present invention, the "predetermined height" may be calculated as in Equation 3 below if the amount of accumulated heat is 200,000 J or more.

[Equation 3]

X/X ₀ = -0.00001 * Y/Y ₀ + 78.3

In Equations 2 to 3, X means the predetermined height, that is, the height [㎛] of the neutron shielding sculpture to be cut, and Y means the amount of accumulated heat [J]. In addition, X ₀ means 1 μm, Y ₀ means 1 J.

The step (c) may be performed at a temperature lower than the melting point of the metal base material and higher than the melting point of the metal powder. When the step (c) is performed at a temperature higher than the melting point of the metal base material, the base material is melted and the quality of the object may be reduced. When the step (c) is performed at a temperature lower than the melting point of the metal powder, the workability of the metal may be rapidly reduced.

Step (b) and step (c) may be performed simultaneously or at the same time, and preferably, may be performed simultaneously, but is not limited thereto.

The metal base material includes one selected from the group consisting of aluminum (Al), titanium (Ti), nickel (Ni), chromium (Cr), iron (Fe), stainless steel, tungsten (W), and combinations of two or more thereof and preferably, may include titanium, but is not limited thereto.

The metal powder may include one selected from the group consisting of aluminum (Al), iron (Fe), stainless steel, copper (Cu), tungsten (W), and a mixture of two or more thereof, preferably, aluminum may be included, but is not limited thereto.

As a non-limiting example of the present invention, the metal base material to the metal powder are respectively ferritic stainless steel, austenitic stainless steel, martensitic stainless steel, and combinations of two or more thereof. It may include one selected from the group consisting of, but is not limited thereto.

The ceramic powder is boron carbide (Boron carbide), boron oxide (Boron oxide), boron nitride (Boron nitride), cadmium carbide (Cadmium carbide), cadmium oxide (Cadmium oxide), cadmium nitride (Cadmium nitride), indium carbide (Indium carbide), indium oxide (Indium oxide), indium nitride (Indium nitride), samarium carbide (Samarium carbide), samarium oxide (Samarium oxide), samarium nitride (Samarium nitride), hafnium carbide (Hafnium carbide), hafnium Hafnium oxide, Hafnium nitride, Europium carbide, Europium oxide, Europium nitride, Gadolinium carbide, Gadolinium oxide oxide), gadolinium nitride, and may include one selected from the group consisting of a mixture of two or more thereof, and preferably, may include boron carbide, but is not limited thereto.

The ceramic content of the neutron shielding sculpture may be 5 to 50% by weight based on the total weight of the neutron shielding sculpture. If the content of the ceramic belongs to 5 to 50% by weight, preferably, 24 to 26% by weight, the occurrence of cracks can be reduced.

Sculpture for neutron shielding

The neutron shielding sculpture according to another aspect of the present invention may be manufactured by the above-described manufacturing method.

The neutron shielding sculpture may be composed of a cermet derived from metal and ceramic. Unlike the conventional cermet sculptures that are formed in a plate-like shape by the extrusion method and are cut and joined after cutting, the neutron shielding sculpture may include a curved surface such as a cylinder, or have a shape such as a folded structure without a joint surface.

The metal may include one selected from the group consisting of aluminum (Al), iron (Fe), stainless steel, copper (Cu), tungsten (W), and mixtures of two or more thereof, preferably, aluminum can, but is not limited thereto.

As a non-limiting example of the present invention, the metal is one selected from the group consisting of ferritic stainless steel, austenitic stainless steel, martensitic stainless steel, and combinations of two or more thereof. may include, but is not limited thereto.

The ceramic is boron carbide (Boron carbide), boron oxide (Boron oxide), boron nitride (Boron nitride), cadmium carbide (Cadmium carbide), cadmium oxide (Cadmium oxide), cadmium nitride (Cadmium nitride), indium carbide ( Indium carbide, indium oxide, indium nitride, samarium carbide, samarium oxide, samarium nitride, hafnium carbide, hafnium oxide (Hafnium oxide), hafnium nitride, europium carbide, europium oxide, europium nitride, gadolinium carbide, gadolinium oxide ), may include one selected from the group consisting of gadolinium nitride (Gadolinium nitride) and a mixture of two or more thereof, and preferably, may include boron carbide, but is not limited thereto.

The ceramic content of the neutron shielding sculpture may be 5 to 50% by weight based on the total weight of the neutron shielding sculpture. If the content of the ceramic belongs to 5 to 50% by weight, preferably, 24 to 26% by weight, the occurrence of cracks can be reduced.

Hereinafter, embodiments of the present invention will be described in detail with reference to the accompanying drawings.

Comparative Examples 1 to 6

A metal base material was prepared in order to manufacture a neutron shielding sculpture using the direct energy fusion stacking method (DED). The metal powder and ceramic powder were melted by irradiating the laser while supplying the metal powder and the ceramic powder on the metal base material through the powder supply device. At this time, the powder carrier gas (carrier gas) was supplied at a rate of 3 L / min in the chamber. Metal powders and ceramic powders, each having a powder size of 50 to 100 μm, was used, and the power of the powder supplying drum motor was maintained at 0.1 to 1.5 W. In addition, the laser scan speed was maintained at 5 to 10 mm/s, and the laser power was maintained at 150 to 240 W. Then, a cermet layer was formed by solidifying the molten metal and ceramic by a laser, and the cermet layer was repeatedly formed to obtain a neutron shielding object having a ceramic content of 20 to 35 wt%.

Specific process conditions are shown in Table 1 below.

Item comparative example One 2 3 4 5 6 metal base material SUS304 SUS304 SUS304 SUS304 SUS304 SUS304 metal powder component Al Al Al Al Al Al ceramic powder ingredients B ₄ C B ₄ C B ₄ C B ₄ C B ₄ C B ₄ C Laser power (W) 180 180 180 180 180 180 Scan speed (mm/s) 6 6 6 6 6 8 Specific energy (J/mm ² ) 125 125 125 125 125 93.75 number of stacks One 2 3 4 One One

Examples 1-6

Except for changing the process conditions as shown in Table 2 below, a neutron shielding sculpture having a ceramic content of 20 to 33 wt% was obtained in the same manner as in Comparative Example 1.

Item Example One 2 3 4 5 6 metal base material Ti Ti Ti Ti Ti Ti Laser power (W) 220 220 220 180 180 180 Scan speed (mm/s) 6 6 6 6 6 6 Specific energy (J/mm ² ) 152.8 152.8 152.8 125 125 125 number of stacks One One One 2 3 4

Hereinafter, embodiments of the present invention will be described in more detail. However, the following experimental results describe only representative experimental results among the above examples, and the scope and content of the present invention cannot be construed as being reduced or limited by the examples. Each effect of various embodiments of the present invention not explicitly presented below will be specifically described in the corresponding section.

Experimental Example 1. Analysis of factors that cause cracks inside the sculpture

3 is an SEM image of a crack (macro crack) generated inside a specimen for neutron shielding according to a comparative example of the present invention. 4 and 5 are images taken with a metal microscope and SEM images of micro cracks generated inside the specimen for neutron shielding according to a comparative example of the present invention, respectively.

Referring to FIGS. 3 to 5 , it can be seen that a number of cracks are generated inside the specimen for neutron shielding regardless of whether the specific energy or the number of layers is changed.

Then, in order to analyze the effect of the components of the base material on the crack generation and peeling of the sculpture, thermal expansion analysis using COMSOL MULTIPHYSICS was performed. Based on the image of the sculpture specimen taken with an optical microscope, a rectangular parallelepiped base material of 8 mm * 8 mm * 3 mm was shaped at an ambient temperature of 25 °C. And the radiative cooling phenomenon of the upper surface of the specimen was described by reflecting the emissivity of the material, and the convective cooling phenomenon was described for the entire surface of the exposed specimen.

Referring to FIG. 6( a ), it can be seen that the peak temperature of the titanium metal base material is higher than that of SUS304.

Referring to FIG. 6(b) , it can be seen that the von Mises stress of a metal base material such as titanium, tungsten, and aluminum is lower than that of SUS 304.

Through thermal expansion analysis, it can be seen that titanium, which can achieve a temperature sufficient to melt the metal powder, and has a low stress value at the interface between the base material and the object, is preferable as the base material component.

7 and 8 are images taken with a metal microscope and SEM images of micro cracks generated inside the specimen for neutron shielding according to an embodiment of the present invention, respectively.

Referring to FIGS. 7 and 8 , it can be seen that cracks are reduced when a sculpture is manufactured by applying a base material including titanium.

Experimental Example 2. Analysis of the microstructure of the sculpture

In the manufacturing process of the neutron shielding sculpture, the mixed layer formed at the boundary between the base material and the sculpture needs to be removed because the shielding performance is poor. However, since the thickness of the mixed layer to be formed varies according to process conditions, removing the mixed layer by measuring the thickness of the mixed layer each time causes inefficiency of the process. Therefore, a method for easily predicting the thickness of the mixed layer by analyzing the relationship between the process variable and the thickness of the mixed layer was studied.

To analyze the relationship between the total heat input applied to the base material and the thickness of the mixed layer among various process variables, the amount of heat accumulated and the average thickness of the mixed layer of the sculpture according to an embodiment of the present invention were measured.

Specifically, the neutron shielding sculpture according to an embodiment of the present invention was photographed with an optical microscope to confirm the mixed layer in which the boundary melting phenomenon occurred, and the distance between the straight line connecting both ends of the boundary and the boundary at the top of the straight line was 16 points. was measured in At this time, the effect of changing the thickness of the mixed layer due to the non-uniformity of the surface was neglected.

9 is a graph showing the average thickness of the removed mixed layer with respect to the amount of heat accumulated in the manufacturing process of the sculpture according to an embodiment of the present invention (black) and a graph showing the thickness to which a margin of 10% is added (red) ) is shown together.

Referring to FIG. 9 , it can be seen that the average thickness of the mixed layer increases as the amount of accumulated heat increases and eventually converges. Through this, it is possible to estimate the thickness of the mixed layer by measuring the amount of heat accumulated in the base material, and furthermore, it can be seen that the sculpture can be economically manufactured by optimizing the thickness of the mixed layer to be removed.

Experimental Example 3. Phase identification

In order to confirm that the neutron shielding sculpture is stably manufactured according to the manufacturing method of the present invention, XRD (X-Ray Diffraction) analysis was performed on the neutron shielding sculpture manufactured according to a comparative example and an embodiment of the present invention. carried out.

10 (a) to 10 (b) shows the analysis results of the neutron shielding sculpture manufactured according to a comparative example of the present invention, and FIGS. 11 (a) to 11 (c) are in an embodiment of the present invention It shows the analysis result of the neutron shielding sculpture manufactured according to the method.

10 and 11, the neutron shielding sculpture according to a comparative example and an embodiment of the present invention _{mainly contains Al and B 4} C as reactants, but some unreacted materials to metals and ceramics are reacted. It can be seen that AlB ₂ , C, Al ₄ C ₃ , and AlB ₁₂ C ₂ are also included. However, since the peak intensity of components other than C is very low, it can be seen that the amount of impurities produced is very small, and furthermore, it can be seen that a sculpture for neutron shielding can be stably manufactured.

Experimental Example 4. Diversification of the shape of the neutron shielding body

In order to check whether the neutron shielding sculptures of various shapes can be manufactured according to the manufacturing method of the present invention, the neutron shielding sculptures manufactured according to an embodiment of the present invention were photographed.

12 and 13 are images of the process of manufacturing the plate-shaped neutron shield and the cylindrical neutron shield according to the manufacturing method of the present invention.

12 and 13, in the case of manufacturing a neutron shielding sculpture using additive manufacturing technology, various types of neutron shielding bodies can be easily manufactured by changing three-dimensional shape data, so the shielding body which was considered a limitation of the prior art It is possible to innovatively change the shape of the shield, and it is possible to manufacture a shield with a complex shape required by the device or part in which the shield is used. In addition, it can be seen that the separation problem that occurs when manufacturing the structure of the spent nuclear fuel storage container can be solved.

The description of the present invention described above is for illustration, and those of ordinary skill in the art to which the present invention pertains can understand that it can be easily modified into other specific forms without changing the technical spirit or essential features of the present invention. will be. Therefore, it should be understood that the embodiments described above are illustrative in all respects and not restrictive. For example, each component described as a single type may be implemented in a distributed manner, and likewise components described as distributed may be implemented in a combined form.

The scope of the present invention is indicated by the following claims, and all changes or modifications derived from the meaning and scope of the claims and their equivalents should be construed as being included in the scope of the present invention.

1: metal
2: Ceramic
3: metal base material

Claims (9)

(a) preparing a metal base material;
(b) supplying a metal powder and a ceramic powder to at least a portion of the upper surface of the metal base material;
(c) melting the metal powder and the ceramic powder by irradiating a laser; and
(d) solidifying the product of step (c) to form a cermet layer;
Steps (b) to (d) are performed one or more times to produce a sculpture having a predetermined shape, a method for producing a neutron shielding sculpture. According to claim 1,
The (b) step and the (c) step are performed at the same time, the method for producing a neutron shielding sculpture. According to claim 1,
The step (c) is lower than the melting point of the metal base material, and is performed at a temperature higher than the melting point of the metal powder, the method for producing a neutron shielding sculpture. According to claim 1,
(e) cutting the neutron shielding sculpture by a predetermined height and separating it from the metal base material; further comprising, a method for producing a neutron shielding sculpture. According to claim 1,
The metal base material includes one selected from the group consisting of aluminum (Al), titanium (Ti), nickel (Ni), chromium (Cr), iron (Fe), stainless steel, tungsten (W), and combinations of two or more thereof A method of manufacturing a neutron shielding sculpture. According to claim 1,
The metal powder comprises one selected from the group consisting of aluminum (Al), iron (Fe), stainless steel, copper (Cu), tungsten (W), and a mixture of two or more thereof, a method for producing a neutron shielding sculpture. According to claim 1,
The ceramic powder is boron carbide (Boron carbide), boron oxide (Boron oxide), boron nitride (Boron nitride), cadmium carbide (Cadmium carbide), cadmium oxide (Cadmium oxide), cadmium nitride (Cadmium nitride), indium carbide (Indium carbide), indium oxide (Indium oxide), indium nitride (Indium nitride), samarium carbide (Samarium carbide), samarium oxide (Samarium oxide), samarium nitride (Samarium nitride), hafnium carbide (Hafnium carbide) Hafnium oxide, Hafnium nitride, Europium carbide, Europium oxide, Europium nitride, Gadolinium carbide, Gadolinium oxide oxide), gadolinium nitride (Gadolinium nitride), and a method of manufacturing a neutron shielding sculpture comprising one selected from the group consisting of a mixture of two or more thereof. According to claim 1,
The ceramic content of the neutron shielding sculpture is 5 to 50% by weight based on the total weight of the neutron shielding sculpture. A neutron shielding sculpture manufactured by the manufacturing method according to any one of claims 1 to 8.

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