KR20210091106A - Apparatus for spent nuclear fuel storage - Google Patents

Abstract

The present invention relates to a spent nuclear fuel storage apparatus capable of maintaining the temperature of spent nuclear fuel. According to one embodiment of the present invention, the spent nuclear fuel storage apparatus comprises: a storage tank storing spent nuclear fuel and cooling water controlling the temperature of the spent nuclear fuel; a fixing unit located on the upper part of the storage tank, provided with fixing grooves having a concave shape on the inner surfaces corresponding to each other, and provided with a holding unit having a stepped shape protruding along the outer surface and disposed at the upper end of the storage tank; and a reduction module connected to the fixing part and reducing the flow of coolant. The reduction module includes a first vertical portion positioned in a first direction a second vertical portion positioned in a second direction intersecting the first direction and connected to the first vertical portion. Since one end of each of the first vertical portion and the second vertical portion is inserted into the fixing groove and upper movement of the first vertical part and the second vertical part is restricted through a stopper disposed at the upper end of the fixing groove, the first vertical portion and the second vertical portion are primarily fixed and coupled. The fixing unit has a double fixed coupling structure secondarily fixed and coupled to the storage tank through the holding unit part to stably reduce the flow of the coolant in a first direction and a second direction in the coolant.

Description

Spent nuclear fuel storage device {APPARATUS FOR SPENT NUCLEAR FUEL STORAGE}

The present invention relates to a spent nuclear fuel storage system.

The spent nuclear fuel storage system is a water tank that is put in cooling water for the purpose of blocking the radiation generated from the spent nuclear fuel after the operation period is over and suppressing the temperature rise due to the residual reaction.

When a vibration or earthquake occurs in the spent nuclear fuel storage device, the coolant inside the storage tank flows and applies a force to the inner wall of the storage tank, which may cause damage. In addition, if the coolant is lost to the outside of the storage device, secondary damage may occur as the temperature of the spent nuclear fuel inside the storage device rises. Therefore, there is a demand for technology development to prevent the flow of coolant in the spent nuclear fuel storage device or the loss of coolant.

As a related prior document, Korean Patent No. 138,726 discloses "a storage container for defective spent nuclear fuel".

Korean Patent No. 138,726

One embodiment of the present invention suppresses the maximum level of coolant by reducing the flow of coolant due to earthquake or external excitation of the spent nuclear fuel storage device, and self-sloshing even in the event of a power loss accident of the spent nuclear fuel storage device This is to prevent the loss of coolant in advance through reduction, and to maintain the temperature of spent nuclear fuel by minimizing the loss of coolant in the spent nuclear fuel storage device and to prevent secondary damage due to temperature rise in advance.

In addition to the above problems, the embodiment according to the present invention may be used to achieve other problems not specifically mentioned.

A spent nuclear fuel storage device according to an embodiment of the present invention includes a storage tank in which spent nuclear fuel and cooling water controlling the temperature of the spent nuclear fuel are accommodated, and is located at the upper part of the storage tank, and has a fixing groove having a concave shape on the inner surfaces corresponding to each other. and a fixing part having a stepped shape protruding along the outer surface and having a seating part located at the upper end of the storage tank, and a reduction module connected to the fixing part and reducing the flow of cooling water, wherein the reduction module is configured to: a first vertical portion positioned as , a second vertical portion positioned in a second direction intersecting the first direction and connected to the first vertical portion, wherein each of the first vertical portion and the second vertical portion has one end in the fixing groove The upper movement of the first vertical part and the second vertical part is limited through a stopper inserted and positioned at the upper end of the fixing groove, so that the first and second fixed couplings are performed, and the fixing part is secondarily fixedly coupled to the reservoir through the seating part. The flow of the cooling water in the first direction and the second direction is stably reduced in the inside of the unit.

One embodiment of the present invention reduces the flow of coolant in the spent nuclear fuel storage device to minimize the maximum level of coolant and the loss of coolant, and reduces self-sloshing even if an accident in which the power of the spent nuclear fuel storage device is lost occurs. This minimizes the loss of coolant, maintains the temperature of spent nuclear fuel, and has the effect of preventing secondary damage due to temperature rise in advance.

1 is a perspective view schematically illustrating a spent nuclear fuel storage device according to an embodiment of the present invention.
2 is an exploded perspective view schematically illustrating a spent nuclear fuel storage device according to an embodiment of the present invention.
3 is an exploded perspective view schematically illustrating an abatement module of a spent nuclear fuel storage device according to an embodiment of the present invention.
4 and 5 are cross-sectional views schematically illustrating a spent nuclear fuel storage device according to an embodiment of the present invention.
6 is a perspective view schematically illustrating an abatement module of a spent nuclear fuel storage device according to an embodiment of the present invention.
7 and 8 are photographs showing analysis results of the spent nuclear fuel storage device according to an embodiment of the present invention.

With reference to the accompanying drawings, the embodiments of the present invention will be described in detail so that those of ordinary skill in the art to which the present invention pertains can easily implement them. The present invention may be embodied in many different forms and is not limited to the embodiments described herein. In order to clearly explain the present invention in the drawings, parts irrelevant to the description are omitted, and the same reference numerals are used for the same or similar components throughout the specification. In addition, in the case of a well-known known technology, a detailed description thereof will be omitted.

Throughout the specification, when a part "includes" a certain element, it means that other elements may be further included, rather than excluding other elements, unless otherwise stated.

Hereinafter, a spent nuclear fuel storage device will be described in detail with reference to the drawings.

1 is a perspective view schematically showing a spent nuclear fuel storage device according to an embodiment of the present invention, FIG. 2 is an exploded perspective view schematically showing a spent nuclear fuel storage device according to an embodiment of the present invention, and FIG. 3 is An exploded perspective view schematically showing an abatement module of a spent nuclear fuel storage device according to an embodiment of the present invention, and FIGS. 4 and 5 are cross-sectional views schematically showing a spent nuclear fuel storage device according to an embodiment of the present invention, 6 is a perspective view schematically showing an abatement module of a spent nuclear fuel storage device according to an embodiment of the present invention, and FIGS. 7 and 8 are analysis results of a spent nuclear fuel storage device according to an embodiment of the present invention; It's a photo.

In this specification, the x-axis, y-axis, and z-axis shown in FIGS. 1 to 6 are perpendicular to each other, and mean a first direction, a second direction, and a third direction, respectively. The first direction means the direction in which the first vertical part 41 extends in FIG. 1 (the horizontal direction in FIG. 1 ), the second direction is perpendicular to the first direction, and the direction in which the second vertical part 42 extends ( 1), the third direction is perpendicular to both the first direction and the second direction, and the longitudinal direction of the first vertical portion 41 and the second vertical portion 42 (height direction in FIG. 1 ) ) means

1 and 2 , the spent nuclear fuel storage device 1 may include a storage tank 10 , a fixing unit 30 , a reduction module 40 , and a spent nuclear fuel 50 . The spent nuclear fuel storage device 1 may be located in a nuclear fuel storage room (not shown) located in the nuclear reactor building. The spent nuclear fuel storage device 1 may store the spent nuclear fuel 50 after the operation period has expired.

The storage tank 10 may be positioned to extend long in the z-axis direction. The storage tank 10 may accommodate the spent nuclear fuel 50 therein. The storage tank 10 may have a rectangular columnar shape, but is not limited thereto.

The storage tank 10 may accommodate the cooling water 20 . The coolant 20 may suppress a temperature rise due to a residual reaction occurring in the spent nuclear fuel 50 . The cooling water 20 may be connected to a cooling device for cooling water or a water purification device for purifying water.

The fixing part 30 may be located on the upper part of the storage tank 10 . The fixing part 30 may have a shape corresponding to the upper shape of the storage tank 10 . The fixing part 30 may have a quadrangular prism shape.

The fixing part 30 may be detachably attached to the storage tank 10 . The lower side of the fixing part 30 may be inserted into the storage tank 10 , and the upper side of the fixing part 30 may be fixed to the upper end of the storage tank 10 . The inside of the fixing part 30 may be connected to the reduction module 40 and the outside may be connected to the storage tank 10 .

The fixing part 30 may include a seating part 31 , a connection hole 32 , and a connector 33 . The seating part 31 may be located along the outer surface of the fixing part 30 . The seating part 31 may have a stepped shape protruding from the outer surface of the fixing part 30 . The seating part 31 may be located at the upper end of the storage tank 10 .

The connection hole 32 may be located in the seating part 31 . The connection hole 32 may penetrate the seating part 31 in the z-axis direction. The connection hole 32 may be positioned to face the connection hole (not shown) located at the upper end of the storage tank 10 .

The connector 33 may be inserted into the connection hole 32 . The connector 33 may mutually fix the fixing part 30 and the storage tank 10 while sequentially passing through the connection hole 32 of the seating part 31 and the connection hole of the storage tank 10 . The connector 33 may include a bolt, a rivet, or a tox. Since the fixing part 30 can be fixed in a state in which a part is seated in the storage tank 10 through the seating part 31 , structural stability can be improved.

The reduction module 40 may be located in the upper part of the storage tank 10 . The reduction module 40 may be located inside the cooling water 20 . The reduction module 40 may reduce the flow of the cooling water 20 . The reduction module 40 may be made of a metal material with high corrosion resistance. The reduction module 40 may be made of stainless steel or nickel, but is not limited thereto.

The reduction module 40 may be connected to the inside of the fixing part 30 . The reduction module 40 may be detachably attached to the fixing part 30 . The user can monitor the state of the reduction module 40 by detaching the reduction module 40 from the fixing part 30 as necessary. In addition, the user can monitor the state of the reduction module 40 through the sensor attached to the reduction module (40). When an abnormality is detected in the reduction module 40 , the user may wash or replace the reduction module 40 .

The reduction module 40 may include a first vertical portion 41 and a second vertical portion 42 . The first vertical portion 41 and the second vertical portion 42 may be positioned to cross each other. The first vertical portion 41 and the second vertical portion 42 may have a cross shape that is orthogonal to each other.

The first vertical portion 41 may extend long in the x-axis direction. The first vertical part 41 may be positioned between the yz inner surfaces of the pair of fixing parts 30 positioned opposite to each other in the x-axis direction. The first vertical portion 41 may include a first partition wall 44 and a second partition wall 45 .

The first partition wall 44 may extend long in the x-axis direction. One side of the first partition wall 44 may be connected to the inner surface of the fixing part 30 . The other side of the first partition wall 44 may be connected to the second partition wall 45 . The second partition wall 45 may extend long in the x-axis direction. The second partition wall 45 may be positioned on a straight line with the first partition wall 44 in the x-axis direction. One side of the second partition wall 45 may be connected to the first partition wall 44 . The other side of the second partition wall 45 may be connected to the inner surface of the fixing part 30 .

The second vertical portion 42 may extend long in the y-axis direction. The second vertical part 42 may be positioned between the xz inner surfaces of the pair of fixing parts 30 positioned opposite to each other in the y-axis direction. The second vertical portion 42 may include a third partition wall 46 and a fourth partition wall 47 .

The third partition wall 46 may extend long in the y-axis direction. One side of the third partition wall 46 may be connected to the inner surface of the fixing part 30 . The other side of the third partition wall 46 may be connected to the fourth partition wall 47 . The fourth partition wall 47 may extend long in the y-axis direction. The fourth partition wall 47 may be positioned on a straight line with the third partition wall 46 in the y-direction. One side of the fourth partition wall 47 may be connected to the third partition wall 46 . The other side of the fourth partition wall 47 may be connected to the inner surface of the fixing part 30 .

The first partition wall 44 may be positioned to be mutually perpendicular to the third partition wall 46 , and the third partition wall 46 may be positioned to be mutually orthogonal to the second partition wall 45 , and the second partition wall 45 . may be positioned to be mutually orthogonal to the fourth partition wall 47 , and the fourth partition wall 47 may be positioned to be mutually orthogonal to the first partition wall 44 .

The reduction module 40 may reduce the flow of the coolant 20 in the coolant 20 . The first vertical portion 41 may reduce the flow of the coolant 20 in the x-axis direction, and the second vertical portion 42 may reduce the flow of the coolant 20 in the y-axis direction.

Conventionally, when a vibration occurs in a spent nuclear fuel storage tank due to an earthquake or external excitation, a loss of coolant may occur due to a sloshing phenomenon of the internal coolant, and secondary damage may occur as the temperature of the spent nuclear fuel rises. could

On the other hand, in the spent nuclear fuel storage device 1 , even when vibration or earthquake occurs, the reduction module 40 sloshes the coolant 20 in the x-axis direction and the y-axis direction inside the coolant 20 . It is possible to prevent the phenomenon in advance and reduce the flow of the cooling water 20 .

Accordingly, the spent nuclear fuel storage device 1 can lower the maximum water level of the coolant 20 of the coolant 20 through the reduction module 40 , and the coolant 20 is lost to the outside of the storage tank 10 . Since it can be minimized, the temperature of the spent nuclear fuel 50 can be maintained at a low temperature.

In addition, in the spent nuclear fuel storage device 1, the reduction module 40 can self-reduce the sloshing phenomenon itself without an additional system, so even if an accident of power loss of the nuclear fuel storage device occurs, the spent nuclear fuel 50 It is possible to prevent secondary damage due to the temperature increase of

Referring to FIG. 3 , the fixing part 30 may include a fixing groove 34 , a stopper 35 , and a fixing hole 36 . The fixing groove 34 may be located on the inner surface of the fixing part 30 . The fixing groove 34 may have a concave groove shape in a direction toward the outside of the fixing part 30 .

The fixing grooves 34 are two pairs, each located on the same line along the z-axis with one end of the first partition wall 44 , the second partition wall 45 , the third partition wall 46 , and the fourth partition wall 47 . can One end of each of the first partition wall 44 , the second partition wall 45 , the third partition wall 46 , and the fourth partition wall 47 may be inserted into the fixing groove 34 .

Referring to the enlarged circle of FIG. 3 , the stopper 35 may be located at the upper end of the fixing groove 34 . The stopper 35 may have a shape in which an upper portion extends to both sides along the y-axis direction and a lower portion extends along the z-axis direction. The stopper 35 may have a T-shape.

The upper portion of the stopper 35 may be positioned in contact with the upper end of the fixing unit 30 . A lower portion of the stopper 35 may be inserted into the fixing groove 34 in the z-axis direction. When the partition walls 44, 45, 46, 47 are inserted into the fixing groove 34, the stopper 35 closes the partition walls 44, 45, 46, and 47 at the upper end of the partition walls 44, 45, 46, 47. It can be fixed to the fixing part (30).

The fixing hole 36 may be located in the stopper 35 . The fixing hole 36 may penetrate the stopper 35 in the z-axis direction. The fixing hole 36 may be positioned to face the fixing hole (not shown) located at the upper end of the fixing part 30 . A fastener such as a bolt, rivet, or tox may be inserted into the fixing hole 36 to fix the stopper 35 to the upper end of the fixing unit 30 .

In the spent nuclear fuel storage device (1), even when the flow of the coolant (20) is large, the bulkheads (44, 45, 46, 47) are fixed through the fixing groove (34), the stopper (35), and the fixing hole (36). Since it is firmly fixed to the top 30 and can stably reduce the flow of the cooling water 20 , the reliability of reducing sloshing can be improved.

In addition, the spent nuclear fuel storage device 1 primarily fixes and couples the first bulkhead 44 , the second bulkhead 45 , the third bulkhead 46 and the fourth bulkhead 47 to the fixing part 30 , , this fixed structure may be secondarily fixedly coupled to the storage tank 10 . Therefore, since the storage tank 10 and the reduction module 40 can be double-coupled, the stability and rigidity of the fixing can be improved.

Referring to FIG. 4 , the water level of the cooling water 20 may be the length from the lower end of the storage tank 10 to the water surface 21 . The height d2, which is the length of the reduction module 40 in the z-axis direction, may be 20% or more and 40% or less of the water level of the cooling water 20 .

In this case, the reduction module 40 can effectively reduce the maximum flow level of the cooling water 20 . When the height d2 of the reduction module 40 is less than 20% of the water level of the cooling water 20, the flow reduction efficiency of the cooling water 20 may be lowered, and when it exceeds 40% of the water level, the reduction module 40 Manufacturing costs can be high.

The first vertical portion 41 and the second vertical portion 42 may be inserted into the upper portion of the storage tank 10 in a state connected to the reduction module 40 . The height d4 , which is the length of the first vertical portion 41 and the second vertical portion 42 in the z-axis direction, may be 20% or more and 40% or less of the water level of the coolant 20 .

The lower side of the first vertical part 41 and the second vertical part 42 may be located inside the cooling water 20 and the upper side may be located above the water surface 21 of the cooling water 20 . When the upper ends of the first vertical portion 41 and the second vertical portion 42 are located above the water surface 21 , the separation distance d1 between the upper ends of the vertical portions 41 and 42 and the water surface of the cooling water 20 . ) may be 5% or less of the height d4 of the vertical portions 41 and 42 . When the separation distance d1 between the upper end of the first vertical portion 41 and the second vertical portion 42 and the water surface of the cooling water 20 is greater than 5% of the height d4 of the vertical portions 41 and 42, The sloshing reduction efficiency of the cooling water 20 may be reduced.

Referring to FIG. 5 , upper ends of the first vertical part 41 and the second vertical part 42 may be located below the water surface 21 of the coolant 20 . That is, the first vertical portion 41 and the second vertical portion 42 may be located in a state submerged in the coolant 20 .

When the first vertical portion 41 and the second vertical portion 42 are located below the water surface 21 , the separation distance d3 between the lower ends of the vertical portions 41 and 42 and the water surface of the coolant 20 is It may be 20% or more and 40% or less of the water level of the cooling water 20 . When the distance d3 between the lower ends of the first and second vertical portions 41 and 42 and the water surface of the cooling water 20 is out of the range of 20% or more and 40% or less of the water level of the cooling water 20, The sloshing reduction efficiency of the cooling water 20 may be reduced.

The separation distance d1 between the upper end of the first vertical portion 41 and the second vertical portion 42 and the water surface of the cooling water 20 is 5% or less of the height d4 of the vertical portions 41 and 42, or vertical When the separation distance d3 between the lower ends of the parts 41 and 42 and the water surface of the coolant 20 is 20% or more and 40% or less of the coolant level 20 , the vertical parts 41 and 42 are the coolant 20 . It can be located near the free surface with the greatest velocity. Accordingly, the reduction module 40 can suppress the flow of the coolant 20 near the water surface 21 , which has the largest flow speed of the coolant 20 at the fluid speed potential, thereby increasing the sloshing reduction efficiency.

6 is similar to the reduction module 40 of FIG. 3 except for the third vertical part 43, so the same reference numerals are used for the same parts, and a detailed description thereof will be omitted.

Referring to FIG. 6 , the reduction module 40 may include a third vertical part 43 . The third vertical portion 43 may be positioned between the first vertical portion 41 and the second vertical portion 42 . The third vertical part 43 may connect the first vertical part 41 and the second vertical part 42 . The third vertical portion 43 may be detachably connected to the first vertical portion 41 and the second vertical portion 42 by inserting a fastener such as a bolt, rivet, or tox, respectively. The third vertical portion 43 may have a rhombus shape connected to ends of the first vertical portion 41 and the second vertical portion 42 .

The third vertical portion 43 may include a fifth partition wall 431 , a sixth partition wall 432 , a seventh partition wall 433 , and an eighth partition wall 434 . The fifth partition wall 431 may be positioned between the first partition wall 44 and the third partition wall 46 . The fifth barrier rib 431 may be positioned to extend diagonally between the x-axis extended by the first barrier rib 44 and the y-axis extended by the third barrier rib 46 . The fifth partition wall 431 may connect the first partition wall 44 and the third partition wall 46 .

The sixth partition wall 432 may be positioned between the third partition wall 46 and the second partition wall 45 . The sixth barrier rib 432 may extend diagonally between the y-axis extended by the third barrier rib 46 and the x-axis extended by the second barrier rib 45 . The sixth partition wall 432 may connect the third partition wall 46 and the second partition wall 45 .

The seventh partition wall 433 may be positioned between the second partition wall 45 and the fourth partition wall 47 . The seventh barrier rib 433 may be positioned to extend diagonally between the x-axis extended by the second barrier rib 45 and the y-axis extended by the fourth barrier rib 47 . The seventh partition wall 433 may connect the second partition wall 45 and the fourth partition wall 47 .

The eighth barrier rib 434 may be positioned between the fourth barrier rib 47 and the first barrier rib 44 . The eighth barrier rib 434 may be positioned to extend diagonally between the y-axis extended by the fourth barrier rib 47 and the x-axis extended by the first barrier rib 44 . The eighth barrier rib 434 may connect the fourth barrier rib 47 and the first barrier rib 44 .

The reduction module 40 includes a first vertical part 41 in the x-axis direction, a second vertical part 42 in the y-axis direction, and a first vertical part 41 and a second vertical part ( 42) may include a third vertical portion 43 positioned diagonally between the x-axis direction, the y-axis direction, and the flow of the coolant 20 in the diagonal direction between the x-axis and the y-axis can be reduced. . Accordingly, the spent nuclear fuel storage device 1 can prevent the sloshing phenomenon of the coolant 20 through the reduction module 40 and minimize the loss of the coolant 20 .

Hereinafter, the present invention will be described in more detail using the cooling water flow analysis example. These examples are merely for illustrating the present invention, and the present invention is not limited thereto.

Coolant flow analysis

Example 1

A spent nuclear fuel storage device including an abatement module in a storage tank is manufactured. The storage tank is a rectangular tank with a width of 1.3 m and a height of 2.115 m. The height of the cooling water is 1.525 m, and the ratio (h/W) of the height of the cooling water to the width of the square water tank is 1.173. The analysis excitation condition was the sinusoidal excitation of the first sloshing mode of the cooling water 20 as an input, and the validity and validity of the analysis method were verified through experiments.

7 is an analysis result of the flow state of the coolant 20 of the spent nuclear fuel storage device for comparing the maximum sloshing height according to the change in the height of the vertical portion 42 of the reduction module 40. As shown in FIG. Referring to FIG. 7 , the height of the vertical portion 42 is 50 mm, 100 mm, 150 mm, 200 mm, 250 mm, 300 mm, 350 mm, 400 mm, 450 mm, and 500 mm in order from (a) to (j).

Analysis result of Example 1

Referring to FIG. 7 , in the case of (a) of FIG. 7 where the height of the vertical part 42 is 50 mm, it can be seen that the maximum height of the free water surface of the cooling water 20 is 215 mm. Each of the vertical portions 42 has a height of 100 mm. In the case of 150mm, 20mm, 250mm, and 300mm of FIG. 7 (b) to (f), it can be seen that the maximum height of the free water surface of the cooling water 20 decreases to 90mm, 60.5mm, 39mm, 28mm, and 16mm, respectively. there is. In the case of (g) to (j) of FIG. 7 where the height of the vertical part 42 is 350mm, 400mm, 450mm, and 500mm, respectively, it can be seen that the maximum height of the free water surface of the cooling water 20 converges to 13mm. .

As the height of the vertical portion 42 increases, it can be seen that the maximum height of the free water surface decreases. When the height of the vertical portion 42 is 300 mm or more, it can be seen that the maximum free water level is 5% or less of the maximum free water level without the vertical portion 42 .

Example 2

A spent nuclear fuel storage device including an abatement module in a storage tank is manufactured. The storage tank is a rectangular tank with a width of 1.3 m and a height of 2.115 m. The height of the cooling water is 1.525 m, and the ratio (h/W) of the height of the cooling water to the width of the square water tank is 1.173. The analysis excitation condition was the sine wave excitation of the first sloshing mode of the cooling water 20 as an input, and the validity and validity of the analysis method were verified through experiments.

8 shows the separation distance between the water surface of the cooling water 20 and the top of the vertical part 42 in order to compare the maximum sloshing height according to the change in the installation position of the vertical part 42 of the reduction module 40 (a) to (j) These are the analysis results performed with different settings up to

Analysis result of Example 2

Referring to FIG. 8 , it can be seen that the sloshing height of the free water surface changes according to the separation distance between the vertical part 42 and the water surface of the cooling water 20 before it. It can be seen that the maximum height of the free water surface due to sloshing decreases as the separation distance between the water surface of the cooling water 20 and the upper end of the vertical portion 42 decreases. It can be seen that the maximum height of the free water surface decreases as the separation distance between the vertical portion 42 and the water surface of the entire cooling water 20 decreases from (a) to (j). It can be seen that as the separation distance between the vertical portion 42 and the entire surface of the cooling water 20 decreases, the vertical portion 42 interferes with the behavior of the cooling water 20 and thus sloshing is reduced.

Although the preferred embodiment of the present invention has been described in detail above, the scope of the present invention is not limited thereto, and various modifications and improvements by those skilled in the art using the basic concept of the present invention as defined in the following claims are also provided. is within the scope of the

1: spent nuclear fuel storage device 10: storage tank
20. Coolant 21. Sleep
30. Fixing part 31. Seating part
32. Connection hole 33. Connection hole
34. Fixing groove 35. Stopper
36. Fixing hole 37. Insert
38. Insertion hole 40. Reduction module
41. First vertical portion 42. Second vertical portion
43. Third vertical part 44. First bulkhead
45. Second bulkhead 46. Third bulkhead
47. Fourth bulkhead 431. Fifth bulkhead
432. 6th bulkhead 433. 7th bulkhead
434. 8th bulkhead 50. Spent nuclear fuel

Claims (8)

a storage tank in which the spent nuclear fuel and cooling water controlling the temperature of the spent nuclear fuel are accommodated;
A fixing part located in the upper part of the storage tank, provided with a fixing groove of a concave shape on the inner surface corresponding to each other, having a stepped shape protruding along the outer surface and provided with a seating part located at the upper end of the storage tank, and
A reduction module connected to the fixing part and reducing the flow of the coolant
including,
The reduction module,
a first vertical portion positioned in a first direction;
a second vertical portion positioned in a second direction intersecting the first direction and connected to the first vertical portion
includes,
The first vertical portion and the second vertical portion are respectively one end inserted into the fixing groove and the upper movement of the first vertical portion and the second vertical portion is restricted through a stopper located at the upper end of the fixing groove 1 It is a double fixed coupling structure that is fixedly coupled to a car, and the fixing part is secondarily fixedly coupled to the storage tank through the seating part, and stably reduces the flow of the coolant in the first direction and the second direction in the coolant Spent nuclear fuel storage. In claim 1,
A length of the first vertical portion and the second vertical portion in a third direction perpendicular to the first and second directions is 20% or more and 40% or less of a water level of the coolant. In claim 2,
When the upper ends of the first vertical portion and the second vertical portion are located above the water surface of the cooling water, the separation distance between the first vertical portion and the second vertical portion and the water surface of the cooling water is the first vertical portion and A spent nuclear fuel storage device that is 5% or less of a length of the second vertical portion in a third direction. In claim 3,
When the upper ends of the first vertical part and the second vertical part are located below the water surface of the coolant, the separation distance between the lower ends of the first vertical part and the second vertical part and the water surface of the coolant is equal to the water level of the coolant. Spent fuel storage of 20% or more and 40% or less. In claim 1,
The first vertical part includes a first bulkhead connected to one side of the fixing part, and a second bulkhead having one side connected to the first bulkhead and the other side connected to the other side of the fixing part. In claim 5,
The second vertical part includes a third bulkhead connected to one side of the fixing part, and a fourth bulkhead having one side connected to the third bulkhead and the other side connected to the other side of the fixing part. In claim 6,
and a third vertical portion positioned between the first vertical portion and the second vertical portion and connecting the first vertical portion and the second vertical portion. In claim 7,
The third vertical portion includes a fifth barrier rib interconnecting the first barrier rib and the third barrier rib, a sixth barrier rib interconnecting the third barrier rib and the second barrier rib, and the second barrier rib and the fourth barrier rib A spent nuclear fuel storage device comprising: a seventh bulkhead connecting the second bulkhead; and an eighth bulkhead interconnecting the fourth and first bulkheads.

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