1. Field of the Invention
The present invention relates to a container, and particularly relates to a radioactive contaminant container for containing radioactive contaminants.
2. Background Art
In the related art, a radioactive contaminant container for safely containing radioactive contaminants has been known (for example, refer to Japanese Unexamined Patent Application Publication No. 2007-147580). Japanese Unexamined Patent Application Publication No. 2007-147580 discloses a mobile radiation shielding container formed in order to safely reserve radioactive wastes generated in a medical field for waste treatment or to store radioactive materials. The mobile radiation shielding container is a heavy radiation shielding container formed by heavy metals such as lead in order to contain a radioactive waste introducing receptacle or a radioactive material storing bucket. The radiation shielding container disclosed in Japanese Unexamined Patent Application Publication No. 2007-147580 has an opening and closing lid on an upper surface or a lateral surface thereof in order to insert the radioactive waste introducing receptacle. The upper surface of the lid of the radiation shielding container has an introducing hole for introducing the radioactive waste into the radioactive waste introducing receptacle, and is formed to cover a surface of the introducing hole with the lid for shielding radiation generated from the inside. In order for the radiation shielding container to be movable, a caster is attached to a lower portion of the radiation shielding container.
However, the mobile radiation shielding container disclosed in Japanese Unexamined Patent Application Publication No. 2007-147580 is proposed on the premise that the container is used in a medical field, and is not intended to store a large amount of radioactive contaminants. For example, when an accident of a nuclear power plant results in a large amount of the radioactive contaminants, all of the radioactive contaminants cannot be immediately purified. Accordingly, it becomes necessary to store the radioactive contaminants for temporary isolation from a living space or for permanent isolation for the purpose of disposal. When the mobile radiation shielding container disclosed in Japanese Unexamined Patent Application Publication No. 2007-147580 is used to store a large amount of the radioactive contaminants, lead is used in the mobile radiation shielding container in order to enhance radiation shielding efficiency. Accordingly, it is apprehended that the lead adversely affects the environment.
In addition, in order to move a container which becomes heavy due to use of heavy metals such as lead, a caster is attached to the above-described mobile radiation shielding container. Therefore, when the mobile radiation shielding container disclosed in Japanese Unexamined Patent Application Publication No. 2007-147580 is used to store the radioactive contaminants, it is necessary to have an extra space inside a storing space in order to contain the caster portion. In addition, in order to store a large amount of the radioactive contaminants, it is necessary to provide many containers. In this case, in order to save the storing space, it is required to store the containers by stacking the container thereon. However, since the mobile radiation shielding container disclosed in Japanese Unexamined Patent Application Publication No. 2007-147580 has the attached caster, it is difficult to safely stack the container thereon.
Therefore, the present invention aims to provide a radioactive contaminant container which can enhance radiation shielding efficiency even by using materials of low environmental load and can save a storing space, when storing radioactive contaminants by using multiple containers.
In order to achieve the above-described object, a radioactive contaminant container according to the present invention includes a wall that defines a containing space for containing radioactive contaminants and shields at least a portion of radiation irradiated from the radioactive contaminants, and the wall has an outer shape of a hexagonal cylinder or a substantially hexagonal cylinder. The term “radioactive contaminants” means a substance contaminated by radioactive substances.
The term “wall” does not depend on a positional relationship when the radioactive contaminant container is placed on a predetermined plane. For example, when the radioactive contaminant container is placed on a predetermined plane so that an axial direction of the hexagonal cylinder or the substantially hexagonal cylinder is perpendicular to the plane, the wall is configured to include all of an upper surface, a lateral surface and a bottom surface of the hexagonal cylinder or the substantially hexagonal cylinder. Similarly, for example, even when the radioactive contaminant container is placed on a predetermined plane so that the axial direction of the hexagonal cylinder or the substantially hexagonal cylinder is parallel to the plane, the wall is configured to include all of the upper surface, the lateral surface and the bottom surface of the hexagonal cylinder or the substantially hexagonal cylinder.
For example, the wall includes a first protrusion extending along the axial direction of the hexagonal cylinder or the substantially hexagonal cylinder and protruding outward; and a first recess extending along the axial direction and recessed inward, and the first recess can be fitted to the first protrusion formed in the other radioactive contaminant container.
In the description of the invention, the term “outward side” represents a farther side from the center of the radioactive contaminant container unless otherwise described, and the term “inward side” represents a closer side from the center of the radioactive contaminant container unless otherwise described.
As an example, the wall may include a first surface and a second surface, each extending in a direction intersecting with the axial direction of the hexagonal cylinder or the substantially hexagonal cylinder, and each shape being hexagonal or substantially hexagonal. Any one surface of the first surface and the second surface may include a second protrusion protruding outward, and the other surface may include a second recess recessed inward. The second recess may be fitted to the second protrusion formed in the other radioactive contaminant container.
The wall may include a metal plate having multiple through-holes. For example, a portion of the wall may be formed to be attachable to and detachable from the other portion of the wall, or to be openable and closeable in order to contain the radioactive contaminants in the containing space.
As an example, the wall may include a layer containing radiation shielding materials having at least silicon, strontium, magnesium, europium and dysprosium as essential elements. The wall may further include a layer formed of stainless steel. The layer containing the radiation shielding materials may be a layer in which the radiation shielding materials are added to resin or rubber. As another example, the wall may be formed of stainless steel.
For example, the radioactive contaminant container according to the present invention may contain a reverse osmosis membrane used to purify radioactively contaminated water. In addition, a radioactive contaminant container according to the present invention may be configured such that a containing space for containing radioactive contaminants contains multiple radioactive contaminant containers according to the present invention.
As an example, the first recess may be disposed on three surfaces which are not adjacent to each other within six surfaces extending in the axial direction of the hexagonal cylinder or the substantially hexagonal cylinder, and a handle for attaching a wire rope for transportation may be disposed in the first recess.
In a radioactive contaminant container according to the present invention, since a wall has an outer shape of a hexagonal cylinder or a substantially hexagonal cylinder, when multiple radioactive contaminant containers are juxtaposed, it is possible to juxtapose the adjacent radioactive contaminant containers by bringing the containers into close contact with each other. In addition, the radioactive contaminant containers can be not only juxtaposed, but also stacked. Therefore, when storing the radioactive contaminant containers containing radioactive contaminants, it is possible to save storing space for the radioactive contaminant containers, which is disposed under the ground or on the ground.
In addition, it is possible to juxtapose or stack the radioactive contaminant containers by bringing the containers into close contact with each other. Accordingly, a radiation shielding function obtained by the wall is enhanced by increased thickness at horizontally or vertically adjacent places of the two walls. This can further reduce air dose inside the container and the storing space of the radioactive contaminant container. That is, in order to enhance radiation shielding efficiency of the radioactive contaminant container, it is not necessary to form the radioactive contaminant container by using lead which adversely affects the environment. If the multiple radioactive contaminant containers according to an aspect of the present invention are brought into close contact with each other and are juxtaposed or stacked, it is possible to further enhance the radiation shielding efficiency.
In this manner, according to the radioactive contaminant container of the present invention, the radiation shielding efficiency can be enhanced even by using materials of low environmental load and a storing space can be saved, when storing the radioactive contaminants by using the multiple radioactive contaminant containers.
If the wall includes the first protrusion extending along the axial direction of the hexagonal cylinder or the substantially hexagonal cylinder and protruding outward; and the first recess extending along the axial direction and recessed inward, and if the first recess can be fitted to the first protrusion formed in the other radioactive contaminant container, when juxtaposing multiple radioactive contaminant containers, it is possible to connect the multiple radioactive contaminant containers according to an aspect of the present invention by allowing the first protrusion and the first recess of the adjacent radioactive contaminant containers to be fitted to each other.
Therefore, the multiple radioactive contaminant containers can be further brought into close contact with each other and can be stably stored. In addition, by connecting the radioactive contaminant containers to each other, it is possible to reduce a risk that the radioactive contaminant containers may fall down due to a shock of an earthquake.
If any one surface of the first surface and the second surface in the wall, each shape of which is hexagonal or substantially hexagonal, includes a second protrusion protruding outward, and the other surface includes a second recess recessed inward, and if the second recess can be fitted to the second protrusion formed in the other radioactive contaminant container, when stacking multiple radioactive contaminant containers, it is possible to allow the second protrusion of the lower radioactive contaminant container to be fitted to the second recess of the upper radioactive contaminant container.
Therefore, even when the radioactive contaminant containers are stacked, the multiple radioactive contaminant containers can be further brought into close contact with each other, and can be stably stored by connecting the upper and lower containers. Accordingly, it is possible to reduce a risk that the radioactive contaminant containers may fall down due to a shock of an earthquake.
If the wall is configured to include the metal plate having multiple through-holes, strength of the wall is increased. In addition, since the metal plate has the multiple through-holes, even when a stretching force, a compression force or an impact is applied to the wall, it is possible to mitigate these forces. Therefore, it is possible to increase overall strength of the radioactive contaminant container. As an example, the term “metal plate having multiple through-holes” represents a metal mesh plate.
If in order to contain the radioactive contaminants in the containing space, a portion of the wall is formed to be attachable to and detachable from the other portion of the wall or to be openable and closeable, a portion of the wall functions as a lid. Accordingly, it is possible to facilitate introducing and containing of the radioactive contaminants.
If the wall includes the layer containing the radiation shielding materials having at least silicon, strontium, magnesium, europium and dysprosium as essential elements, it is possible to further enhance the radiation shielding function of the radioactive contaminant container by using the radiation shielding materials of the low environmental load. Similarly, if the layer containing the radiation shielding materials is a layer in which the radiation shielding materials are added to resin or rubber, it is also possible to further enhance the radiation shielding function of the radioactive contaminant container by using the radiation shielding materials of the low environmental load.
If the wall is configured to further include a layer formed of stainless steel or the wall is formed of the stainless steel, since the wall is unlikely to rust, the strength of the wall can be maintained. In addition, it is possible to further enhance the radiation shielding function.
If the radioactive contaminant container according to the present invention is configured to contain a reverse osmosis membrane (RO membrane) used to purify radioactively contaminated water, it is possible to contain and store the reverse osmosis membrane (RO membrane) which becomes the radioactive contaminants through the purification of the radioactively contaminated water, in the radioactive contaminant container having the radiation shielding function.
If the containing space of the radioactive contaminant container according to the present invention is configured to contain other multiple radioactive contaminant containers according to the present invention, the radioactive contaminants contained inside the multiple radioactive contaminant containers are doubly contained in the radioactive contaminant container. Accordingly, it is possible to further enhance the radiation shielding efficiency. Furthermore, the outer shape of the wall in the radioactive contaminant container containing the multiple containers is the hexagonal cylinder or the substantially hexagonal cylinder. Accordingly, the thickness of the wall of the adjacent places is increased by the juxtaposition. Therefore, as described above, it is possible to further enhance the radiation shielding efficiency.
If the first recess is disposed on three surfaces which are not adjacent to each other within six surfaces extending in the axial direction of the hexagonal cylinder or the substantially hexagonal cylinder, and if the handle for attaching the wire rope for transportation is disposed in the first recess, when lifting, transporting and installing the radioactive contaminant container, the radioactive contaminant container can be lifted, transported and installed with a good balance.
Hereinafter, an embodiment of the present invention will be described with reference to the accompanying drawings.
The walls 2 include a detachable lid 2a disposed to be capable of introducing the radioactive contaminants 3 and a main body 2b. In the radioactive contaminant container 1 according to the first embodiment, as illustrated in
In the radioactive contaminant container 1 according to the first embodiment, since widths of lateral surfaces 5 of the main body 2b (width in a direction perpendicular to the axial direction y) are coincidental with each other, the walls 2 have the outer shape of a substantially regular hexagonal cylinder. In the radioactive contaminant container 1 according to the first embodiment, as an example, a length in the axial direction of the substantially regular hexagonal cylinder configured to have the outer shape of the walls 2 is approximately 1 m, and a length of a diagonal line passing through a center of the substantially regular hexagon in a plane of the substantially regular hexagon is approximately 1 m.
As illustrated in
As illustrated in
The lateral surface recess 7 is formed so that the width becomes narrower as it goes inward to the radioactive contaminant container 1. In the radioactive contaminant container 1 according to the first embodiment, when multiple radioactive contaminant containers 1 are juxtaposed, the outward protrusion 6b can be fitted to the lateral surface recess 7 disposed on the other radioactive contaminant container 1.
The lid 2a has a lid protrusion 9 corresponding to the shapes of the lateral surface protrusion 6 and the lateral surface recess 7, and a lid recess 10. When the lid 2a is attached to the main body 2b, the lid protrusion 9 is formed so that an outer edge thereof matches the outward protrusion 6b, and the lid recess 10 is formed so that the outer edge matches the lateral surface recess 7. A lid center projection 11 projecting outward from the radioactive contaminant container 1 is formed in the center of the lid 2a.
In a positional relationship illustrated in
The bottom surface projection 14 is formed at each substantially hexagonal corner which appears on the bottom surface of the radioactive contaminant container 1. As illustrated in
The first lateral wall 14b is disposed to be tilted to the plane 15 and the plane 16. The first lateral wall 14b is tilted so that a cross-sectional surface of the bottom surface projection 14 becomes narrower as it goes outward from the radioactive contaminant container 1. As illustrated in
Next,
In addition, in the inner side of each substantially hexagonal corner portion which appears on the opening surface, an inner wall 25 extending along the axial direction y of the radioactive contaminant container 1 is disposed. As illustrated in
A space 24 is defined between the inner wall 25 and the lateral surface 5. In the lateral surface protrusion 6, a space 27 is defined between a wall surface configuring the inward protrusion 6a and a wall surface configuring the outward protrusion 6b. Since the space 24 and the space 27 are disposed, it is possible to further reduce the weight of the radioactive contaminant container 1 as compared to a case where these spaces are filled.
The containing space 23 of the radioactive contaminant container 1 is defined by the inner wall surface of a portion of the lateral surface 5 and the inner wall surface of the inner wall 25 and the inward protrusion 6a which are extended from the portion of the lateral surface 5. As illustrated in
In the radioactive contaminant container 1 according to the first embodiment, the walls 2 configuring the radioactive contaminant container 1 are reinforced, thereby increasing the strength of the radioactive contaminant container 1.
In the radioactive contaminant container 1 according to the first embodiment, the reinforcing metal plate 28 is also embedded along the lid 2a and the bottom surface inside the lid 2a and the bottom surface. The reinforcing metal plate 28 is also embedded inside the lid center projection 11, the bottom surface projection 14, the lateral surface protrusion 6 and the lateral surface recess 7. That is, in the radioactive contaminant container 1 according to the first embodiment, the reinforcing metal plate 28 is embedded throughout the entire walls 2.
In addition, it is possible to juxtapose or stack the radioactive contaminant containers 1 by bringing the containers into close contact with each other. Accordingly, the thickness is increased at horizontally or vertically adjacent places of the walls 2. Therefore, a radiation shielding function is enhanced by the walls 2. This can further reduce air dose inside the container and the storing space of the radioactive contaminant container 1.
In addition, the lateral surface of the radioactive contaminant container 1 has the outward protrusion 6b and the lateral surface recess 7 which can be fitted together. When the multiple radioactive contaminant containers 1 are juxtaposed, the outward protrusion 6b and the lateral surface recess 7 of the adjacent radioactive contaminant container 1 are fitted together, thereby enabling the connection between the radioactive contaminant containers 1. Therefore, it is possible to further bring the multiple radioactive contaminant containers 1 into close contact with each other and to stably store the containers.
In addition, by connecting the radioactive contaminant containers 1, it is possible to reduce a risk that the radioactive contaminant containers 1 may fall down due to a shock of an earthquake. In addition, in the radioactive contaminant container 1 according to the first embodiment, the inward protrusion 6a is formed inside the outward protrusion 6b. Therefore, when the outward protrusion 6b and the lateral surface recess 7 of the adjacent radioactive contaminant containers 1 are fitted together, the wall thickness of the fitted portion further becomes thicker than the wall thickness of the other portion. Therefore, it is possible to further enhance the radiation shielding function.
Furthermore, the lid 2a and the bottom surface of the radioactive contaminant container 1 have the lid center projection 11 and the multiple bottom surface projections 14. When the multiple radioactive contaminant containers 1 are stacked, the corner portion 18 of the bottom surface projection 14 can be fitted to the notched portion 21 of the lid center projection 11. That is, since the bottom surface projection 14 is formed, the lid center projection 11 can be fitted to a recess of the bottom surface which is formed by the first lateral wall 14b of the bottom surface projection 14 and the plane 16. Therefore, even when the radioactive contaminant containers 1 are stacked, the multiple radioactive contaminant containers 1 can be further brought into close contact with each other, and can be stably stored by connecting the upper and lower containers. Accordingly, it is possible to reduce a risk that the radioactive contaminant containers 1 may fall down due to a shock of an earthquake.
Further, as illustrated in
Hereinafter, the above-described radiation shielding materials will be described in detail. The radiation shielding materials have at least silicon, strontium, magnesium, europium and dysprosium as essential elements. It is possible to shield X-rays in a practicable level by combining the elements. In addition, ultraviolet rays can also be absorbed. Further, since silicate-based compound is used, the specific gravity is lighter than lead and workability is also excellent.
The content of silicon (Si) is preferably 5 to 30 mass %, and more preferably 10 to 20 mass %. The content of strontium (Sr) is preferably 30 to 60 mass %, and more preferably 40 to 50 mass %. The content of magnesium (Mg) is preferably 1 to 20 mass %, and more preferably 5 to 10 mass %. The content of europium (Eu) is preferably 0.1 to 5 mass %, and more preferably 0.5 to 3 mass %. The content of dysprosium (Dy) is preferably 0.1 to 5 mass %, and more preferably 0.5 to 3 mass %.
The above-described radiation shielding materials may contain an oxygen atom (preferably 10 to 50 mass %, and more preferably 20 to 40 mass %) in addition to the above-described essential elements. In addition, a boron atom and a radiation absorbing atom other than the above-described atoms (for example, lanthanoid elements such as erbium) may be contained therein, and further inevitable impurities in production may be contained therein. In view of maleficence, it is preferable that lead elements be not substantially contained therein. For example, the content of the lead is 5 mass % or less, and preferably 1 mass % or less.
The shape of the above-described radiation shielding materials can be appropriately determined depending on the usage of the shielding materials, and for example includes a granular shape (powder), a pellet shape, a block shape, a film shape and a plate shape. The above-described radiation shielding materials can be obtained through powder processing, and can be mixed with other organics (powder shape and fiber shape) to be used in various shielding applications. For example, in a case of the granular shape, an average particle size may be set to 0.1 μm to 1,000 μm, and preferably 1 μm to 100 μm.
In addition, the above-described radiation shielding materials may be independently used as the compound containing the above-described essential elements, or may be used in conjunction with additives such as water, an organic solvent (alcohol, ethers and the like), surfactants, a resin binder, inorganic particles, organic particles and other radiation shielding materials. In addition, it is preferable to use titanium compounds of titanium, titanium oxide simultaneously and the like. This can further improve a shielding performance of ultraviolet rays.
A preferred manufacturing method of the above-described radiation shielding materials includes a calcination process of mixing and baking silicon compounds, strontium compounds, magnesium compounds, europium compounds and dysprosium compounds. More specifically, for example, the radiation shielding materials can be manufactured through mixing and sintering processes of silicon oxide, strontium carbonate (SrCO3), magnesium oxide (MgO), europium oxide (Eu2O3), and dysprosium oxide (Dy2O3). As the silicon oxide, either silicon dioxide (SiO2) or silicon monoxide (SiO) may be used, but silicon dioxide (SiO2) is preferably used in the radiation shielding materials.
A mixing ratio is not particularly limited. For example, it may be set in which silicon oxide is 20 to 60 mass % (preferably 30 to 50 mass %), strontium carbonate is to 60 mass % (preferably 30 to 50 mass %), magnesium oxide is 5 to 40 mass % (preferably 10 to 30 mass %), europium oxide is 0.1 to 5 mass % (preferably 0.2 to 1 mass %) and dysprosium oxide is 0.1 to 5 mass % (preferably 0.2 to 1 mass %).
In addition to the above-described raw materials, boron compounds of boric acid (H3BO3) may be further added thereto. This facilitates electron transfer between metals during the firing, thereby enabling acceleration in an oxidation-reduction effect. A mixing amount of boric acid is not particularly limited, but is preferably 0.1 to 5 mass %, and more preferably 0.5 to 3 mass %. After being mixed, the above-described raw materials may be pulverized by using a grinder such as a ball mill and a rod mill. The materials may not be pulverized, but in a case of the above-described radiation shielding materials, it is preferable to pulverize the materials. For example, a firing temperature may be set to 500° C. to 2,000° C. in an electric furnace, and preferably 1,000° C. to 1,500° C. Firing atmosphere may be either air atmosphere or an inert gas, but is preferably air atmosphere.
The firing time may be appropriately determined depending on a firing temperature and firing atmosphere, but for example, may be set to 10 minutes to 10 hours, and preferably 30 minutes to 5 hours. After the firing process, it is preferable to further add a plasma sintering process. This can improve X-ray absorption to be obtained from the radiation shielding materials.
The plasma sintering may be performed according to the related art, and for example, may be performed at 500° C. to 2,000° C. (preferably 700° C. to 1500° C.) by using a plasma sintering machine. The sintering time may be appropriately determined depending on a sintering temperature, but for example, may be set to 5 minutes to 2 hours, and preferably 10 minutes to 1 hour.
The above-described radiation shielding materials will be further described in detail by using the following examples. Incidentally, the above-described radiation shielding materials are not limited to the following examples.
SiO2 (manufactured by Iwai Chemicals Co., Ltd) of 40 mass %, SrCO3 (manufactured by Honjo Chemical Corporation) of 38.2 mass %, MgO (manufactured by Ube Material Industries, LTD.) of 20 mass %, Eu2O3 (manufactured by NeoMag Co., Ltd.) of 0.4 mass %, Dy2O3 (manufactured by NeoMag Co., Ltd.) of 0.4 mass % and H3BO3 (manufactured by Iwai Chemicals Co., Ltd) of 1 mass % were placed in a ball mill mixer, and were mixed for one hour. Then, the materials were placed in an electric furnace, and firing was performed under the conditions of air atmosphere, 1,300° C. and two hours. After the firing, the materials were naturally cooled to a room temperature, and were pulverized by using the ball mill mixer so that an average particle size thereof became 7 μm. In this manner, the radiation shielding materials in Example 1 were obtained.
A composition ratio of the radiation shielding materials in Example 1 was measured. The measured result was Si of 13.3 mass %, Sr of 42.4 mass %, Mg of 6.23 mass %, Eu of 0.84 mass % Dy of 1.83 mass %, 0 (oxygen atom) of 31.3 mass %, and the remaining was impurities.
The measured result of the specific gravity was 3.7 g/cm3. A qualitative analysis and a fluorescent X-ray analysis were performed in measurement by using an X-ray diffraction apparatus. As a result, Example 1 described above estimated the radiation shielding materials to be Sr2MgSi2O7.Eu3+,Dy3+.
For the radiation shielding materials obtained in Example 1, sintering was further performed at 1,000° C. for approximately 30 minutes by using a plasma sintering machine (manufactured by SPS Syntax Inc., Model No.: SPS-1030). After the sintering, the radiation shielding materials were naturally cooled to a room temperature, and radiation shielding materials (pellet shape and thickness of 3 mm) in Example 2 were obtained.
A lead plate (thickness of 0.3 mm, commercially available) and an aluminum plate (thickness of 3 mm, commercially available) were respectively used in Comparative Example 1 and Comparative Example 2. X-ray Shielding Performance of Radiation Shielding Materials (X-ray Transmission Measurement)
The radiation shielding materials in Example 1 were further processed in a pellet shape (thickness of 3.95 mm) by using a press machine. According to a transmission method, an X-ray transmittance rate was measured for samples of Examples 1 and 2 and Comparative Examples 1 and 2 under a condition in which measured energy was 50 keV, and then a linear absorption coefficient was calculated by using the transmittance rate. The linear absorption coefficient is calculated by dividing the thickness of the sample (cm) from a value obtained by taking natural logarithm of the transmittance rate. The obtained measurement results are illustrated in Table 1.
Ultraviolet Shielding Performance of Radiation Shielding Materials (UV Transmission Measurement)
A transmission rate of ultraviolet rays in Example 1 was measured by using an ultraviolet and visible spectrophotometer (manufactured by Shimadzu Corporation, Model No.: UV2400PC). As a result, in a wavelength of 250 nm to 400 nm, the transmittance rate was 20% or less.
The above-described result shows an excellent linear absorption coefficient, since in Examples 1 and 2 of the radiation shielding materials, it is possible to obtain a sufficiently low transmittance rate with a practical thickness, although the radiation shielding materials cannot compete with lead which is excellent as the X-ray shielding material in Comparative Example 1. In particular, when compared to aluminum in Comparative Example 2, it is appreciated that the radiation shielding materials sufficiently have an excellent linear absorption coefficient.
In addition, in Example 1 of the radiation shielding materials, it is appreciated that the ultraviolet shielding performance is excellent since the transmittance rate of the ultraviolet rays is low. Furthermore, there is an advantageous effect against electron beams.
In addition, the radiation shielding materials have the significantly lower specific gravity than the specific gravity of lead (11.34), and are excellent in workability since the radiation shielding materials can be easily deformed in a granular shape or a plate shape. Therefore, it is appreciated that the radiation shielding materials can be used in various applications or forms.
The radioactive contaminant container 1 may directly contain the radioactive contaminants according to the first embodiment, or may contain the other radioactive contaminant containers after the radioactive contaminants are contained in the other radioactive contaminant containers.
As illustrated in
In the radioactive contaminant container 42 according to the second embodiment, the outer shape configured to have the lid 45 and the main body 43 is a substantially hexagonal cylinder. Accordingly, when multiple radioactive contaminant containers 42 are juxtaposed, the adjacent radioactive contaminant containers 42 can be juxtaposed in close contact with each other. Therefore, as illustrated in
In addition, the length of one side of the substantially hexagon appearing on the plane side and the bottom surface side of the radioactive contaminant container 42 according to the second embodiment is substantially the same as the length of each side of the inner side appearing on the cross-sectional surface of the inner wall surface which defines the containing space 23 (refer to
Hitherto, the embodiments of the present invention have been described. However, the present invention is not limited to the above-described embodiments, and can be modified and changed in various forms based on the technical spirit of the present invention. For example, in the radioactive contaminant container 1 according to the first embodiment, the shape of the inner wall surface which defines the containing space 23 is not limited to the shape (refer to
In the example illustrated in
The radioactive contaminant container 1 according to the first embodiment can contain various radioactive contaminants or containers which contain radioactive contaminants, in addition to the radioactive contaminant container 42 according to the second embodiment. Therefore, depending on a shape and a nature of materials to be contained, it is possible to appropriately determine which form is suitable for the opening of the containing space in the radioactive contaminant container 1 according to the first embodiment.
The wall of the radioactive contaminant container 1 according to the first embodiment includes the outward protrusion 6b extending along the axial direction and protruding outward, and the lateral surface recess 7 extending along the axial direction and recessed inward, but without being limited thereto, and may not include the outward protrusion 6b and the lateral surface recess 7.
The radioactive contaminant container 50 according to another embodiment does not include the outward protrusion 6b extending along the axial direction and protruding outward, and the lateral surface recess 7 extending along the axial direction and recessed inward. The other configurations are the same as those of the radioactive contaminant container 1 according to the first embodiment. The shape of the wall of the radioactive contaminant container 50 which is configured to have a lid 52a and a main body 52b is a substantially regular hexagonal cylinder. A bottom surface end portion recess 57 is formed on the bottom surface side of the place corresponding to the outward protrusion 6b and the lateral surface recess 7 of the radioactive contaminant container 1 according to the first embodiment.
The radioactive contaminant container 1 according to the first embodiment includes the bottom surface recess formed by disposing the bottom surface projection 14, and the lid center projection 11, but without being limited thereto, may not include the above-described bottom surface recess and the lid center projection 11. In addition, even when the bottom surface recess and the lid center projection 11 are included, the shapes thereof are not limited thereto.
The outer shape of the radioactive contaminant container 60 is a substantially regular hexagonal cylinder. A lid center projection 61 whose cross-sectional surface parallel to an upper surface of the lid is a regular hexagon is disposed on the upper surface of the lid. The lateral surface of the lid center projection 61 is tilted so that the area of the above-described cross-sectional surface of the lid center projection 61 becomes narrower as it goes outward. A bottom surface recess 62 whose cross-sectional surface is a hexagon is formed on the bottom surface of the radioactive contaminant container 60. Accordingly, the lid center projection 61 of the other radioactive contaminant container 60 can be fitted to the bottom surface recess 62.
In addition, as another example, without disposing the projections and the recesses such as the outward protrusion 6b, the lateral surface recess 7, the lid center projection 11 and the bottom surface recess on the walls 2 of radioactive contaminant container 1, a radioactive contaminant container may be configured to include a wall of a hexagonal cylinder including a regular hexagonal cylinder.
The radioactive contaminant container 42 according to the second embodiment does not include the projection and the recess for being connected to the other radioactive contaminant container 42, but is not limited thereto. Similarly to the radioactive contaminant container 1 according to the first embodiment, the projection and the recess for being connected to the other radioactive contaminant container 42 may be included.
In the first and second embodiments, the lids 2a and 45 are disposed to be attachable to and detachable from the main bodies 2b and 43, but are not limited thereto. For example, the lids 2a and 45 may be disposed to be openable and closeable with respect to the main bodies 2b and 43.
In the first and second embodiments, the description has been made for clarity of the description by defining the upper surface and the bottom surface, in the positional relationship when the wall of the substantially hexagonal cylinder is placed in the upright position so that the axial direction y in
The wall 2 of the radioactive contaminant container 1 according to the first embodiment adopts a three-layer structure where the intermediate layer 31 formed of the radiation shielding material is interposed between the outer and inner stainless steel layers 30 and 32, but is not limited thereto. For example, a two-layer structure may be adopted where a stainless steel layer is arranged outside and a radiation shielding material-added layer formed by adding a radiation shielding material to a resin or rubber is arranged inside. Similarly, the wall of the radioactive contaminant container 42 according to the second embodiment may also adopt the three-layer structure where the intermediate layer 31 formed of the radiation shielding material is interposed between the outer and inner stainless steel layers 30 and 32, or may also adopt the two-layer structure where the stainless steel layer is arranged outside and the radiation shielding material-added layer formed by adding the radiation shielding material to the resin or rubber is arranged inside. The other configuration may be adopted.
In addition, without using the radiation shielding material, the wall 2 of the radioactive contaminant container 1 may be formed of other materials such as stainless steel. For example, even when the wall 2 of the radioactive contaminant container 1 is formed of only the stainless steel, depending on the thickness of the wall 2, it is possible to shield at least a portion of radiation. When multiple radioactive contaminant containers 1 are juxtaposed, total thickness of the adjacent walls 2 are twice the thickness of the single wall 2, thereby further improving the radiation shielding function. Similarly, without using the radiation shielding material, the wall of the radioactive contaminant container 42 according to the second embodiment may be formed of other materials such as the stainless steel.
In addition, with regard to the radiation shielding materials, the radiation shielding material has been described which has been independently developed by the applicant, but without being limited thereto, other materials having the radiation shielding function may be used as the radiation shielding material.
In the radioactive contaminant container 1 according to the first embodiment described above, when the lid 2a is attached to the main body 2b, the outer edge of the lid recess 10 of the lid 2a may be formed so as to expose a portion of the plane side end portion of the lateral surface recess 7, and a handle may be attached to the plane side end portion of the exposed lateral surface recess 7. The handle is sometimes referred to as a lifting point. When lifting, transporting and installing the radioactive contaminant container 1, it is possible to lift the radioactive contaminant container 1 by attaching a wire rope to the handle. The handle is attached to the three places of lateral surface recess 7 which are disposed on three surfaces not adjacent to each other among six surfaces extending in the axial direction of the substantially hexagonal cylinder. Accordingly, the radioactive contaminant container 1 can be lifted, transported and installed with a good balance. Furthermore, when a partition is disposed in the storing space of the radioactive contaminant container 1, it is possible to fix the handle to the partition in order to prevent falling of the radioactive contaminant container 1. As an example, the shape of the handle is a U-shape, but without being limited thereto, may be any shape if the wire rope can be attached thereto. It is preferable that the height width of the handle be configured so as not to interfere with the fitting to the other radioactive contaminant container 1 when stacking the radioactive contaminant containers 1 on one another.
Number | Date | Country | Kind |
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2012-207384 | Sep 2012 | JP | national |