KR101722342B1 - Radioactive waste storage vessel and manufacturing thereof - Google Patents

Abstract

A radioactive waste storage vessel according to an embodiment of the present invention comprises: a body part provided with an inner receiving space which has an opened upper portion to receive radioactive waste and having a polygonal outer peripheral surface; a lid part which covers the upper portion of the body part and coupled to seal the inner receiving space of the body part, wherein the body part is made of spheroidal graphite cast iron containing 3.2-3.7% of carbon, and a coating layer formed on the peripheral surface of the body part to prevent corrosion. According to an embodiment of the present invention, there is an effect in that the storage capacity of the radioactive waste storage vessel according to the measurement volume is maximized and thus, both the durability and the capacity of the radioactive waste vessel can be ensured effectively.

Description

Technical Field [0001] The present invention relates to a radioactive waste storage vessel and a manufacturing method thereof.

The present invention relates to a radioactive waste storage container and a method of manufacturing the same.

Generally, radioactive waste is an unnecessary radioactive material generated during the process of using nuclear energy in a nuclear power plant, etc., and it is a kind of radioactive material such as various waste coming from a workplace or a laboratory handling a nuclear power plant or a radioactive material such as waste water, fission products, cooling water, And the like.

In the disposal and disposal of such radioactive waste, it is legally stipulated that the effect on the surrounding natural radioactivity should be less than 1/10 of the maximum allowable dose (allowable dose).

The treatment of radioactive waste is different according to the state of the waste, and the explanation is as follows.

First, gaseous waste is stored in a sealed tank, and if the radioactivity falls below the reference value, it is filtered with a high-performance filter (HEPA filter) and then released to the atmosphere. At this time, it is confirmed that the concentration of radioactive material in the air is less than 1/10 of the maximum allowable concentration, and then the radioactive material is released from the exhaust system. Filtration removes more than 99.99% of gaseous waste, and the filter used for filtration is treated as solid waste after the end of its life.

In addition, the liquid waste is collected in a storage tank at a weight concentration of ppb (one billionth or less), the clean water is recycled by using an evaporator, and the residue is made into a stable solid, sealed in an iron drum and stored. At this time, a waste liquid having a low radioactive level and low salinity is filtered and then diluted with a large amount of dried water.

Solid waste can be divided into incombustible and combustible materials. Burned materials are incinerated and then made into ash. They are then put into drums together with incombustibles to be solidified in concrete and stored. The incombustibles are compressed or solidified with a solidifying agent, then put in a steel drum and stored in a power plant or a storage room in a sealed state.

Recently, as the use of nuclear energy has increased, the problem of disposal of waste generated in nuclear power plants has become an important issue.

The above-mentioned methods of disposing of radioactive wastes include a full-layer disposal method of piling up a soil drum by accumulating a waste drum, and a deep disposal method of accumulating a waste drum by digging a cave deep underground, in mountains or under the sea.

These radioactive waste disposal sites should be constructed in solid rock masses or geologically stable areas free from the risk of earthquakes, no risk of subsidence, and no flow of groundwater. In addition, the radioactive waste storage container must satisfy certain conditions of content adequacy as well.

However, it is impossible to predict whether or not the geological environment can be changed for a long time at the time of selecting the waste disposal plant. Therefore, the durability and other chemical deformation of the radioactive waste storage container due to external impact or environment change must be minimized, It is necessary to develop a storage container capable of satisfying both requirements because it must satisfy a certain storage amount of the internal storage container under satisfactory design conditions.

KR 2010-0097821 A

The radioactive waste storage container according to an embodiment of the present invention is intended to effectively enhance the durability of the container in terms of materials and effectively implement the radioactive shielding function of the radioactive waste by using spheroidal graphite cast iron as the main component of the container.

In addition, by applying the spheroidal graphite cast iron to the main material of the radioactive waste container, it is possible to maximize the storage amount of the radioactive waste relative to the storage capacity, thereby minimizing the risk of the waste disposal site and effectively improving the physical structure of the container .

The method of manufacturing a radioactive waste storage container according to an embodiment of the present invention effectively increases the stiffness of the physical structure, maximizing the compression pressure at the time of storing the waste, maximizing the storage capacity of the waste, And to provide a radioactive waste container that simultaneously ensures a shielding function and durability due to an external impact.

The radioactive waste storage container according to the first embodiment of the present invention includes a body portion having an outer circumferential surface having a polygonal shape and an inner accommodating space opened at an upper portion to receive the radioactive waste therein, Wherein the body includes spheroidal graphite cast iron and includes 3.2% to 3.7% of carbon, and a coating layer for preventing corrosion is formed on the outer circumferential surface of the body portion.

The lid part is coupled to the upper surface of the body part and further includes an inner protrusion part protruding from the rim of the lower end of the lid part to be inserted into the inner side space of the body part at a predetermined depth, The protruding portion may be formed of an elastic member which is different from the cover portion.

The edge widths of the corner portions of the upper surface of the body portion may be wider than the widths of the edge portions connecting the upper surfaces of the body portion.

In addition, the lid part may be formed at the lower end surface of the lid part so as to correspond to the width of the upper surface rim of the body part so that the lid part is coupled to the upper surface of the body part and the upper surface rim of the body part is inserted and closed.

The lid part may be formed at an upper surface of the body part and may include an elastic member protruding from an inner surface of a lower edge of the lid part to be inserted into the body cavity at a predetermined depth.

In addition, a plurality of longitudinal receiving grooves may be formed in the lower end surface of the body portion so as to be coupled to the feet of the forklift for transportation in one direction.

A radioactive waste storage container according to a second embodiment of the present invention includes a body portion formed in a cylindrical shape and opened to receive radioactive waste in an internal accommodation space, a body portion covering the body top end opening portion, The body includes spheroidal graphite cast iron and includes 3.2% to 3.7% of carbon, and a coating layer for preventing corrosion is formed on the outer circumferential surface of the body portion.

The lid further includes an inner protrusion formed to protrude from the inner edge of the lid unit to be inserted into the inner space of the inner space of the body for a predetermined depth, the inner protrusion being coupled to the upper surface of the body, And the elastic member may be made of a different material from the lid.

The lid part may be formed at an upper surface of the body part and may have an engaging groove formed along the lower end surface of the lid part corresponding to the rim so that the upper surface rim of the body part is inserted and closed.

The lid part may be formed at an upper surface of the body part and may include an elastic member protruding from an inner surface of a lower edge of the lid part to be inserted into the body cavity at a predetermined depth.

The lower end surface of the body may be formed with a plurality of receiving grooves spaced apart from each other in one direction so that the feet of the forklift can be engaged.

A method of manufacturing a radioactive waste storage container according to an embodiment of the present invention includes the steps of forming a polygonal outer circumferential surface and forming an injection port for injecting a casting into an upper side of the polygonal shape, The outer peripheral surface of the upper edge of the upper mold corresponds to the outer side of the upper edge of the upper surface of the upper mold and the outer peripheral surface of the polygon is formed with a width narrower than the width of the upper edge of the upper mold of the upper mold. A lower mold having a lower end integrally formed with the upper mold, and a lower mold having a lower end integrally formed with the upper mold, wherein the lower mold is integrally formed with the mold, Is inserted into the lower mold receiving space, and both ends of the upper surface are inserted into the upper surface corresponding to the upper opening- And a supporting portion formed so as to have a width wider than the widths in both lateral directions of the figure portion to be supported in the mouth direction, wherein the figure-shaped figure portion is inserted into the upper- Inserting the hollow body into the upper and lower mold receiving spaces so that the supporting portion is inserted into the lower mold and both upper end surfaces of the supporting portion are supported in the inserting direction on the upper side of the upper opening side; The casting containing the spheroidal graphite cast iron in which iron is melted through the upper mold injection port on the space between the inner circumferential surfaces of the accommodation space and magnesium is added is injected to form a body portion having an outer circumferential surface of polygonal shape and having an inner space by one opening , An injection port of a casting is formed on an upper side, A top mold formed in a shape corresponding to the top surface shape of the body and a bottom mold coupled to form a spacing space in the bottom of the top mold, the casting being injected into the space through the injection port, And a step of hermetically coupling the lid part to the upper end surface of the body part opening side.

The hollow body is formed with an inner hollow portion, and an opening extending through the hollow portion to penetrate the support portion is formed. At least one fixed shaft is formed on the hollow portion and the inner hollow portion other than the opening portion, Can be inserted.

A step of forming a plurality of receiving grooves so as to be spaced apart from each other such that the forklift foot is coupled to the lower end of the body after the step of sealing the lid part on the upper end surface of the body part opening part, And coating a coating layer for the coating layer.

The features and advantages of the invention will become more apparent from the following detailed description based on the accompanying drawings.

Prior to that, terms and words used in the present specification and claims should not be construed in a conventional and dictionary sense, and the inventor may properly define the concept of the term in order to best explain its invention It should be construed as meaning and concept consistent with the technical idea of the present invention.

According to one embodiment of the present invention, by maximizing the storage capacity according to the volume volume of the radioactive waste storage container, the durability and storage amount of the radioactive waste container can be effectively secured at the same time.

In addition, by maximizing the compression pressure in the space for accommodating the radioactive waste container, it is possible to further improve the storage capacity of the radioactive waste storage container with respect to the physical space.

By applying the material containing the spheroidal graphite cast iron to the radioactive waste container, it is possible to effectively secure the radioactive shielding function and at the same time to secure the durability in accordance with the external impact, thereby improving the site requirements of the radioactive waste disposal plant, There is an effect that the degree of freedom can be maximized.

In addition, the carbon content of the spheroidal graphite cast iron constituting the radioactive waste container is appropriately controlled to ensure the durability of the waste storage container and the reliability of the radioactive shielding more stably.

1 is an exploded perspective view of a radioactive waste storage container according to a first embodiment of the present invention;
2 is an exploded perspective view according to an embodiment of the closed structure of the radioactive waste storage container of the first embodiment of the present invention;
3 is a bottom perspective view of the lid of the radioactive waste storage container according to FIG. 2;
4 is an exploded perspective view according to another embodiment of the closed structure of the radioactive waste storage container of the first embodiment of the present invention;
FIG. 5 is a bottom perspective view of the lid according to FIG. 4; FIG.
6 is an exploded perspective view according to still another embodiment of the closed structure of the radioactive waste storage container of the first embodiment of the present invention;
7 is a bottom perspective view of the lid portion of Fig. 6;
FIG. 8 is a perspective view including a coupling groove of a foot of a transportation equipment of a radioactive waste storage container according to the first embodiment of the present invention; FIG.
9 is an exploded perspective view of a radioactive waste storage container according to a second embodiment of the present invention;
10 is an exploded perspective view according to an embodiment of the closed structure of the radioactive waste storage container of the second embodiment of the present invention;
11 is a bottom perspective view of the lid of the radioactive waste storage vessel according to FIG. 10;
12 is an exploded perspective view according to another embodiment of the closed structure of the radioactive waste storage container of the second embodiment of the present invention;
13 is a bottom perspective view of the lid according to Fig. 12;
FIG. 14 is an exploded perspective view according to still another embodiment of the closed structure of the radioactive waste storage container of the second embodiment of the present invention; FIG.
FIG. 15 is a bottom perspective view of the lid portion shown in FIG. 14; FIG.
16 is a perspective view including a coupling groove of a foot of a transportation equipment of a radioactive waste storage container according to a second embodiment of the present invention; And
17 to 25 are views showing a manufacturing process of a radioactive waste storage container according to an embodiment of the present invention.

BRIEF DESCRIPTION OF THE DRAWINGS The objects, particular advantages and novel features of one embodiment of the present invention will become more apparent from the following detailed description taken in conjunction with the accompanying drawings and the preferred embodiments thereof. It should be noted that, in the present specification, the reference numerals are added to the constituent elements of the drawings, and the same constituent elements are assigned the same number as much as possible even if they are displayed on different drawings. Also, the terms "one side," " first, "" first," " second, "and the like are used to distinguish one element from another, no. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS In the following description of the present invention, a detailed description of known arts which may unnecessarily obscure the gist of an embodiment of the present invention will be omitted.

Hereinafter, one embodiment of the present invention will be described in detail with reference to the accompanying drawings, in which like reference numerals refer to like elements.

1 is an exploded perspective view of a radioactive waste storage container according to a first embodiment of the present invention.

The radioactive waste storage container 1 according to an embodiment of the present invention includes a body portion 10 having an inner receiving space opened at an upper portion to receive radioactive waste therein and having a polygonal outer circumferential surface, And a lid part 20 which covers the upper part of the body 10 and is coupled to seal the space inside the body part 10. The body part 10 includes spheroidal graphite cast iron, Carbon, and a coating layer 12 for preventing corrosion is formed on the outer circumferential surface of the body portion 10. [

1, the radioactive waste storage container 1 according to an embodiment of the present invention includes a body 10 and a lid 20 separately manufactured to accommodate the radioactive waste in the body 10 And has a structure in which the lid portion 20 is closed after being loaded in the space. The lid portion 20 is coupled to the upper surface of the body portion 10 with the screw b. However, various methods other than the screw fastening method can be applied to the fastening method, It is not.

The radioactive waste storage container (1) according to an embodiment of the present invention is basically defined by law as the allowable range of the radioactive shielding function. And a structure and material of a range that satisfies this requirement should be applied. In particular, the radioactive waste storage vessel must not only be shielded from internal radioactivity stably during the storage period, but also must satisfy both the external impact and the structural durability due to the external environment. For this reason, requirements for treatment plants are generally very strictly applied to radioactive waste storage containers, and problems with various follow-up measures due to radioactive hazards near the relevant treatment plants may arise.

In addition, due to various epidemiological studies that take into consideration the risk of earthquake and subsidence, and so on, even if the designated radioactive waste storage facility is treated, the relevant geological factors may be changed by various environments. Various efforts are being made to develop a radioactive waste storage container that can be exposed to external shocks and various environmental changes and can perfectly cope with such environmental impacts.

In addition to the stability in consideration of the durability of such a radioactive waste storage container 1, one embodiment of the present invention can minimize leakage of radioactivity within an allowable range, The present invention provides a radioactive waste storage container (1) having improved technical reliability that meets the standards of the legal system and its manufacturing process.

The radioactive waste storage container 1 according to the first embodiment of the present invention is formed with a body portion 10 having an inner accommodating space opened at the top so as to receive the radioactive waste therein.

As shown in FIG. 1, the body portion 10 forms a rim portion 11 having a polygonal outer circumferential surface so as to form an inner accommodation space. In the first embodiment of the present invention, a quadrangular storage container is shown. However, various polygonal structures can be selectively applied by the stacking and embedding structure of the radioactive waste storage container according to the geographical location and the physical structure. The polygonal body portion 10 is formed to have a width W2 that is wider than the width W1 of the rim portion 11 connecting the respective corners to minimize the durability of each corner portion and the risk of external impact. By doing so, it is possible not only to improve the compactness and design freedom with respect to the adjacent radioactive waste storage container when the polygonal shape is embedded, but also to secure the stiffness of the corner portion in the polygonal shape at the same time.

The body portion 10 includes cast iron, which includes spheroidal graphite cast iron, and contains 3.2% to 3.7% carbon (C) for radiation shielding effect. When the content of carbon (C) is less than 3.2%, it is difficult to effectively realize the shielding effect of radioactivity. When the content of carbon (C) exceeds 3.7%, it is difficult to effectively realize the rigidity of the entire body 10 together with the spheroidal graphite cast iron. Therefore, it is preferable that the body portion 10 includes carbon (C) in the range of 3.2% to 3.7% in order to secure the reliability with respect to the external environment through the rigidity of the body portion 10 together with the radiation shielding Do. Therefore, in addition to the radiation shielding effect, the radioactive waste contained in the radioactive waste storage container can be stably stored even when the external impact is 45 kg · f / mm 2 or more.

The body 10 may be formed with a corrosion-preventing coating layer 12 through a rust-preventive process in order to prevent corrosion of the entire outer circumferential surface together with the cover 20 described later. By forming the coating layer 12, it is possible to appropriately cope with external environmental conditions that can be continuously changed when being stored for a long period of time, and to effectively maintain the outflow of radioactivity and the durability of the waste storage container.

1, the lid part 20 covers the upper part of the body part 10 so as to be coupled to the body part 10 so as to effectively seal the radioactive waste placed on the space inside the body part 10. [ do. In order to more effectively secure the sealing force of the radioactive waste storage container, the lid part 20 can be applied to various embodiments of the sealing structure, and the related details will be described later.

3 is a bottom perspective view of the lid of the radioactive waste storage container according to the first embodiment of the present invention. Fig. 4 is a cross-sectional view of the radioactive waste storage container according to the first embodiment of the present invention. Fig. 5 is a bottom perspective view of the lid according to Fig. 4, Fig. 6 is an exploded view according to another embodiment of the radioactive waste storage container sealing structure of the first embodiment of the present invention, Fig. Fig. 7 is a bottom perspective view of the lid part of Fig. 6; Fig.

2 and 3, the cover 10 is inserted into the inner surface of the rim 11 of the upper surface of the body 10 to a predetermined depth to seal the interior space of the body 10, An inner protruding portion 21 protruding from the inside of the rim 11 on the lower surface of the lower portion of the portion 20 is continuously formed. The inner protruding portion 21 is formed to have an elastic force of the elastic member and is formed with an inner protruding portion 21 so as to form an area equal to or wider than the area inside the rim portion 11 on the upper surface of the body portion 10, The space between the edge 11 of the lid 20 and the inside of the upper edge 11 of the body 10 is completely removed when the body 20 is coupled to the body 10, ) Can be sealed.

4 and 5, the lid part 20 is coupled to the upper surface of the body part 10, and the upper surface rim part 11 of the body part 10 is inserted An engaging groove 22 may be formed on the lower end surface of the lid portion 20 so as to correspond to the width of the upper surface rim portion 11 of the body portion 10 to be hermetically sealed.

An engaging groove 22 formed along the rim is formed on the lower end face of the corresponding lid portion 20 so as to completely insert the upper face rim portion 11 of the body portion 10. [ The coupling groove 22 is made of a material having elasticity such as a separate elastic member so that the coupling groove 22 and the upper surface frame portion 11 of the body portion 10 can be tightly inserted and coupled . By doing so, it is possible to completely seal the space for accommodating the inside of the body portion 10 by the lid portion 20. In this case, not only the engaging groove 22 of the lid part 20 but also any part of the upper surface frame part 11 of the body part 10 to be inserted can be secured with a fixing force and a sealing force at the same time by applying an elastic member or the like.

6 and 7, the lid part 20 is coupled to the upper surface of the body part 10, and the lower end surface rim 11 of the lid part 20 is connected to the upper surface part of the body part 10. [ And a receiving portion 23 including an elastic member may be formed to protrude from the inner surface of the body portion 10 and be inserted into the receiving space of the body portion 10 at a predetermined depth. In this case, the entire inner side surface of the lower end of the lid part 20 protrudes from the receiving part 23, so that not only can the opening part of the body part 10 be completely sealed, but also the radioactive waste There is an advantage that a more stable sealing structure can be realized by applying the same pressure.

The radioactive waste can be safely stored and accommodated through the outer wall of the body portion 10 including the above-mentioned airtight structure and the spheroidal graphite cast iron. Even if the outer surface of the body portion 10 is made with a predetermined thickness in consideration of durability, the outer wall of the body portion 10 including the spheroidal graphite cast iron and manufactured by a manufacturing process described later can withstand even a strong compression pressure. By doing so, it is possible not only to increase the storage amount of waste of up to 20% or more of the conventional steel material storage capacity, but also to increase the reliability of durability including the radiation leakage and the rigidity of the storage container.

Next, as shown in Fig. 8, in order to effectively secure the safety during transportation of the radioactive waste storage container generally carried and loaded by the forklift, a plurality of receiving grooves (for example, 13) can be installed. By joining the feet of the forklift truck to the receiving recess 13, it is possible to prevent any breakage or falling that may occur during transportation of the radioactive waste storage container 1 in advance. It is obvious to those skilled in the art that such a receiving groove 13 can be appropriately changed in design depending on the structure and method of the conveying device.

9 is an exploded perspective view of a radioactive waste storage container according to a second embodiment of the present invention.

The radioactive waste storage container 1a according to the second embodiment of the present invention includes a body 10a formed in a cylindrical shape and opened to receive radioactive waste in the internal space, And a lid part 20a coupled to an upper end of the body part 10a so as to close a space for accommodating the body part 10a. The body part 10a includes spheroidal graphite cast iron, % Carbon, and a coating layer 12a for preventing corrosion is formed on the outer peripheral surface of the body portion 10a.

As shown in Fig. 9, the radioactive waste storage container according to the second embodiment of the present invention has a cylindrical outer circumferential surface, and has a structure capable of loading radioactive waste into the internal containment space. The structure of the body 10a and the lid 20a and the coating layer 12a for preventing corrosion are formed on the outer surface of the body 10a according to the first embodiment of the present invention, Is substantially the same as the corresponding configuration of the container 1, and a detailed description thereof will be omitted.

FIG. 10 is an exploded perspective view according to an embodiment of the closed structure of the radioactive waste storage container of the second embodiment of the present invention, FIG. 11 is a bottom perspective view of the cover of the radioactive waste storage container according to FIG. 10, Fig. 13 is a bottom perspective view of the lid according to another embodiment of the radioactive waste storage container sealing structure, Fig. 14 is an exploded perspective view of another embodiment of the radioactive waste storage container sealing structure according to the second embodiment of the present invention, Fig. 15 is a bottom perspective view of the lid part shown in Fig. 14, and Fig. 16 is a perspective view including the receiving recess of the carrying equipment of the radioactive waste storage container according to the second embodiment of the present invention.

Each embodiment of the sealing structure according to the second embodiment of the present invention is substantially the same as the corresponding embodiment of the sealing section 20a of the sealing structure of the first embodiment of the present invention described above, 8 is substantially the same as the corresponding structure of the embodiment of FIG. 8 described above, and a detailed description thereof will be omitted, and the corresponding structure will be omitted here.

10 and 11, a sealing structure according to an embodiment of the present invention includes a lid portion 11a at the lower end surface of the lid portion 20a so as to be inserted into a receiving space of the body portion 10a at a predetermined depth, The inner protruding portion 21a protruding from the inside of the body portion 10a is inserted to be inserted into the inner side surface of the rim portion 11a of the body portion 10a. 2 and 3, and only the shape of the outer circumferential surface of the body portion 10a is different from that of the lid portion 20 of Figs.

12 and 13, a sealing structure according to another embodiment of the present invention includes a lid portion 20a on the lower end surface corresponding to the rim portion 11a on the upper surface of the body portion 10a, And a coupling groove 22a is formed. This is substantially the same as the contents of the engagement groove 22 of the related lid 20 of Figs. 4 and 5, and a detailed description thereof will be omitted.

14 and 15, a sealing structure according to another embodiment of the present invention includes a cover body 20a having a bottom edge corresponding to a predetermined depth insertion / And a receiving portion 23a having an inner side surface protruding in a coupling direction. The description of the related constitution is substantially the same as the description of the related constitution of Figs. 6 and 7, and a detailed description thereof will be omitted.

The receiving groove 13a in which the coupling means of the conveying equipment such as the foot of the forklift disposed on the lower end face of the body portion 10a according to the second embodiment of the present invention shown in Fig. 16 can be fastened, 8, the description will be omitted.

17 to 25 are views showing a manufacturing process of a radioactive waste storage container according to an embodiment of the present invention.

Hereinafter, the manufacturing process of the radioactive waste storage container according to the first embodiment of the present invention will be described as an example. The manufacturing process of the radioactive waste storage container according to the second embodiment may be the same, The design modification of the structure of each mold according to the structure is within a range obvious to a person skilled in the art.

A method of manufacturing a radioactive waste storage container according to an embodiment of the present invention includes forming an injection port 32 through which a casting is injected into an upper portion of a polygonal outer surface, And the outer surface of the rim portion 41 is formed on the outer side of the other upper surface rim portion 31 of the upper mold 30. The upper surface of the upper rim portion 30 of the upper mold 30, , Preparing a lower mold (40) having an upper surface frame portion (41) corresponding to the upper surface frame (30) and forming a polygonal outer surface with a width narrower than the width of the upper surface frame portion (11)

(51) which is inserted into the inner peripheral surface of the upper mold (30) so as to form a spaced space of a predetermined thickness from the inner peripheral surface of the upper accommodating space (30), a lower end integrally formed in the upper surface (50) including a support portion (52) formed to have a width wider than the width in both lateral directions of the figure portion (51) so that both ends of the upper surface are supported in the inserting direction on the upper opening-side frame- , ≪ / RTI >

The figure 51 of the male mold 50 is inserted into the space for accommodating the upper mold 30 and the support portion 52 of the male is inserted into the space inside the lower mold 40, Inserting the inner mold (50) into the interior space of the upper mold (30) and the lower mold (40) so that the upper ends of the upper molds (30) are supported in the upper insertion direction on the inner side surface (31)

A casting including a spheroidal graphite cast iron in which iron is melted through the injection port 32 of the upper mold 30 and magnesium is added onto the space between the outer peripheral surface of the core mold 50 and the inner peripheral space of the upper mold 30, Forming a body portion 10 having an outer peripheral surface of the polygon and having an inner accommodation space by one opening,

(61) formed with a casting inlet (61a) at an upper end thereof and formed in a shape corresponding to an upper surface top shape of the opening of the body part (10), and a lower mold (62), injecting a casting material through the injection port into the spacing space, and forming a lid part (20) to be hermetically sealed to the upper end surface of the opening part of the body part

 And the lid part (20) is hermetically coupled to the upper end surface of the body part (10).

First, as shown in Fig. 17, the upper mold 30 is prepared. As described above, the upper mold 30 is formed with an inner space to form a polygonal outer circumferential surface of the radioactive waste storage container according to the first embodiment. An injection port 32 for injecting the casting is formed on the upper side, and an opening is formed in the direction toward the lower side, and an inner space forming a polygonal outer circumferential surface is formed on the inner side.

Next, as shown in FIG. 18, the lower mold 40 is prepared in a direction opposite to the opening of the upper mold 30. The lower mold 40 is engaged with the upper mold 30 so that the later-described central mold 50 is inserted into the upper mold 30 and the lower mold 40. [ The lower mold 40 is formed to correspond to the opening of the upper mold 30 and the width of the upper frame 41 of the lower mold 40 is formed to be narrower than the width of the upper side frame 31 on the side of the upper mold 30. Since the outer line of the upper edge portion 41 of the lower die 40 is formed to coincide with the outer line of the edge portion 31 of the upper surface of the upper die 30, the width of the inner side of the lower die 40 corresponds to the correspondence of the upper die 30 (See Fig. 20).

Next, as shown in Fig. 19A, the step of preparing the central mold 50 is described. The mold half 50 is formed to be inserted between the upper mold 30 and the lower mold 40 and inserted into the inner space of the upper mold 30 to be inserted into the inner space of the inner space of the body 10, 51 and a support portion 52 inserted into the inner space of the lower mold 40 and formed integrally with the graphic portion 51. The support portion 52 is formed to be wider than both side widths (width in the longitudinal direction) of the graphic portion 51 (corresponding to a structure in which the width of the inner side of the lower portion 40 is wider than the width of the inner side of the upper portion 30) , So that both upper end surfaces of the support portion 52 can be inserted so as to be partially supported on the corresponding surface of the upper surface rim portion 31 of the upper mold 30 (see Fig. 20). Details will be described later.

19B, the inner die 50 forms an inner hollow portion 53 penetrating through the graphic portion 51 and the support portion 52. As shown in Fig. That is, it is possible to minimize the gas generation by forming the inner hollow portion 53 of the conical shape 50 which is not in direct contact with the casting to be injected. The shape of the inner hollow portion 53 is not particularly defined, but an inner hollow portion 53 can be formed such that the lower end of the support portion 52 is opened, as shown in Fig. 19B. By inserting at least one fixed padding 54 on the area of the inner padding 50 other than the hollow portion 53 in order to firmly support the frame shape by only the portion of the padding 50 excluding the hollow portion 53 , It is possible to more firmly maintain the frame of the central mold 50. [

20, the inner mold 50 is inserted into the upper mold 30 and the lower mold 40, respectively, and then the casting is injected through the injection port 32 opened to one side of the upper mold 30 . Here, the casting may be a casting containing a spheroidal graphite cast iron in which iron is melted and magnesium is added. The figure 51 of the inner mold 50 is inserted into the inner space of the upper mold 30 so that the inner space inner circumferential surface of the upper mold 30 and the outer circumferential surface of the mold 51 have a predetermined thickness Thereby forming the outer circumferential surface of the polygonal body portion 10. The support portion 52 of the inner mold 50 is inserted into the lower mold 40 so that both ends are supported on both sides of the lower mold 40 to prevent the inner mold 50 from shaking in the longitudinal direction in both directions, Can be precisely fixed in the inner space of the upper mold 30. The upper surface of the support portion 52 is supported in the direction of the inner space of the upper mold 30 and a part of the upper surface frame portion 31 of the upper mold 30 so that not only the longitudinal direction, It is possible to accurately control the structural shape and the numerical value of the body 10 to be manufactured by fixing the position in the up and down direction which is the inner space of the upper mold.

21, the upper mold 30 and the lower mold 40 are removed, and when the mold half 50 is removed, the body portion 10 having the outer peripheral surface of the polygon finally and having the inner accommodating space, .

Next, as shown in Fig. 22, the upper mold 61 and the lower mold 62 for forming the lid 20 are prepared. An upper mold 61 having a casting inlet 61a formed at an upper end thereof and a lower mold 62 corresponding to the upper mold 61 and coupled at a lower portion with a spacing space therebetween. Here, the spacing space is formed in such a shape that the lid portion 20 is formed by injecting a casting, which will be described later, and the spacing space can be coupled to the upper edge portion of the body portion 10. By doing so, it is possible to precisely seal the accommodation space inside the body part 10. [ Although not described in detail, in the preparation stage of the upper mold 30 and the lower mold 40 of the lid portion 20 of this step, the structure of the lid portion 20 for the various sealing structures of the radioactive waste storage container substantially as described above To create the framework of.

Next, as shown in Fig. 23, casting is injected into the injection port 61a at the upper end of the upper mold 61. Then, as shown in Fig. Herein, the main component of the casting is the casting containing the spheroidal graphite cast iron in which iron is melted and magnesium is added as described above. By doing so, after removing the upper mold 61 and the lower mold 62, it is possible to manufacture the lid portion 20 capable of sealing the opening portion of the body portion 10 as shown in Fig.

25, a coating layer 12 for preventing corrosion can be further formed on the outer circumferential surface of the entire radioactive waste storage container to which the lid portion 20 and the body portion 10 are coupled through a rustproofing process . By forming the coating layer 12, it is possible to maintain the durability and radioactivity shielding function of the radioactive waste storage container with higher reliability by preventing the corrosion due to the external environment due to the characteristics of the storage container to be stored for a long time.

8 and 16, a plurality of longitudinal receiving grooves 13 are formed at the lower end of the body 10 to facilitate the transportation of transportation equipment such as a forklift truck (not shown) Step < / RTI > This can be easily implemented through a structural modification of the inner space of the associated mold, so that the related drawings will be referred to Figs. 8 and 16. Fig.

The detailed description of the structure of the body 10 and the lid 20 in the construction described in the present manufacturing method is the same as that of the corresponding body of the radioactive waste storage container 1, 1a according to the first and second embodiments Substantially the same as the configuration of the lid sections 10 and 10a and the lid sections 20 and 20a, and a duplicate description will be omitted.

While the present invention has been particularly shown and described with reference to exemplary embodiments thereof, it is to be understood that the present invention is not limited to the disclosed exemplary embodiments, but various changes and modifications may be made without departing from the scope of the present invention. It will be apparent that modifications and improvements can be made by those skilled in the art.

It will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.

1, 1a: Radioactive waste storage container
10, 10a: body part 11, 11a:
12, 12a: Coating layer 13, 13a:
20, 20a: lid part 21, 21a: inner protruding part
22, 22a: coupling groove 23, 23a:
w1: width in the longitudinal direction w2: width in the edge portion
B: fastening means
30: upper figure 31: upper figure
32: Inlet port 40: Lower mold
41: Lower mold edge portion 50:
51: Shapes 52: Supports
53: hollow portion 54: fixed core
61: Upper mold 61a:
62: Lower mold

Claims (14)

A body portion having an inner receiving space opened at an upper portion thereof so that the radioactive waste is directly received therein and having a polygonal outer circumferential surface; And
And an upper portion of the upper surface of the body portion, which is protruded from the rim portion so as to be inserted into a predetermined depth to be inserted into the inner side surface of the body portion inside space to seal the inside space of the body portion by covering the opened upper portion of the body portion, And an inner protrusion formed of an elastic member is formed so as to be in close contact with each other so as to form a larger or equal area,
Wherein the body portion comprises spheroidal graphite cast iron to withstand external impacts of at least 45 kgf / mm < 2 >, including 3.2% to 3.7% carbon,
Wherein a coating layer for preventing corrosion is formed on the outer circumferential surface of the body part, the coating layer being formed on the outer circumferential surface of the body part so that a width of the corners of the body part is wider than a width of a rim connecting the corners. delete delete The method according to claim 1,
Wherein the lid part is coupled at an upper surface of the body part,
Wherein a coupling groove is formed on a lower surface of the lid part so as to correspond to the width of the rim of the upper surface of the body part so that the rim of the upper surface of the body part is inserted and closed. The method according to claim 1,
Wherein the lid part is coupled at an upper surface of the body part,
And a receiving and coupling part protruding from an inner surface of a lower end of the cover part and including an elastic member inserted into the receiving space of the body part to a predetermined depth. The method according to claim 1,
Wherein the lower end surface of the body portion has a plurality of longitudinal direction receiving grooves formed side by side in one direction so that the feet of the transportation forklift can be engaged. delete delete delete delete delete delete delete delete

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