Nuclear power plant having improved safety for earthquake

Abstract

The present invention relates to a nuclear power plant with improved safety against earthquakes, wherein the reactor is a small modular reactor having a core and a steam generator arranged inside, and is extended in a first direction and includes a containment vessel that accommodates the reactor; a concrete structure that surrounds the containment vessel and is spaced apart from the containment vessel; and a first support structure that supports the containment vessel on the concrete structure, wherein the first support structure includes a first support arm, one end of which is connected to the containment vessel and the other end of which protrudes toward the concrete structure; a first protruding structure that protrudes from the concrete structure toward the containment vessel, overlaps at least a portion with the first support arm in the first direction, and is located on the upper part of the first support arm; and a first support unit, one end of which is connected to the first support arm and the other end of which is connected to the first protruding structure.

Description

Technology Field

[0001] The present invention relates to a nuclear power plant with improved safety against earthquakes. Background Technology

[0002] When an earthquake occurs at a nuclear power plant site, seismic forces are transmitted through the ground beneath the power plant structures to the reactor building, which includes the concrete pool housing the reactor. These seismic forces are then transmitted to the containment vessel through its lower or lateral supports, and finally, to the reactor through its lower or lateral supports.

[0003] The development of nuclear power plants that attenuate these seismic forces and enhance reactor safety is required. Prior art literature

[0004] Korean Patent Publication No. 2017-0129867 (Published Nov. 27, 2017) The problem to be solved

[0005] Therefore, the objective of the present invention is to provide a nuclear power plant with improved safety against earthquakes. means of solving the problem

[0006] The objective of the present invention is achieved by a nuclear power plant with improved safety against earthquakes, wherein the reactor is a small modular reactor having a core and a steam generator arranged inside, and a containment vessel that is elongated in a first direction and accommodates the reactor; a concrete structure that surrounds the containment vessel and is spaced apart from the containment vessel; and a first support structure that supports the containment vessel on the concrete structure, wherein the first support structure comprises: a first support arm, one end of which is connected to the containment vessel and the other end of which protrudes toward the concrete structure; a first protruding structure that protrudes from the concrete structure toward the containment vessel, and at least a portion of which overlaps with the first support arm in the first direction and is located on the upper part of the first support arm; and a first support unit, one end of which is connected to the first support arm and the other end of which is connected to the first protruding structure.

[0007] The first support unit above may include a chain.

[0008] The first support unit may further include a circular seismic spring coupled to the chain.

[0009] The above circular seismic spring is connected to the above first protruding structure, and the above chain may be connected to the above first support arm.

[0010] The first support unit may further include a damping member that is extended along the first direction, has one end connected to the end of the first support arm, and the other end connected to the concrete structure.

[0011] The apparatus further includes a second support structure that supports the above-mentioned containment vessel on the above-mentioned concrete structure, wherein the second support structure may include: a second support arm having one end connected to the above-mentioned containment vessel and the other end protruding toward the above-mentioned concrete structure; a second protruding structure protruding from the above-mentioned concrete structure toward the above-mentioned containment vessel, overlapping at least a portion with the second support arm in the first direction, and located at the lower part of the second support arm; and a second support unit having one end in contact with the second support arm and the other end in contact with the second protruding structure.

[0012] The above second support unit may be a seismic isolation unit.

[0013] The first support arm and the second support arm may be located at the same height.

[0014] The first support unit and the second support unit are each provided in multiple numbers and may be arranged alternately along the circumference of the containment vessel. Effects of the invention

[0015] According to the present invention, a nuclear power plant with improved safety against earthquakes is provided. Brief explanation of the drawing

[0016] FIG. 1 shows a nuclear power plant with improved safety against earthquakes according to an embodiment of the present invention, and FIG. 2 shows in detail a first support structure in a nuclear power plant according to an embodiment of the present invention, and FIG. 3 shows in detail a second support structure in a nuclear power plant according to an embodiment of the present invention, and FIG. 4 shows the arrangement relationship between the first support structure and the second support structure in a nuclear power plant according to an embodiment of the present invention. Specific details for implementing the invention

[0017] Hereinafter, various embodiments of the present invention will be described in detail with reference to the attached drawings so that those skilled in the art can easily implement the present invention. The present invention may be embodied in various different forms and is not limited to the embodiments described herein.

[0018] To clearly explain the present invention, parts unrelated to the explanation have been omitted, and the same reference numerals are used for identical or similar components throughout the specification.

[0019] In addition, the size and thickness of each component shown in the drawings are depicted arbitrarily for convenience of explanation, so the present invention is not necessarily limited to what is illustrated.

[0020] Hereinafter, a support structure of a containment vessel according to an embodiment of the present invention will be described with reference to FIGS. 1 to 4.

[0021] FIG. 1 shows a containment vessel support structure according to an embodiment of the present invention, FIG. 2 shows a first support structure in detail in a containment vessel support structure according to an embodiment of the present invention, FIG. 3 shows a second support structure in detail in a containment vessel support structure according to an embodiment of the present invention, and FIG. 4 shows the arrangement relationship between the first support structure and the second support structure in a containment vessel support structure according to an embodiment of the present invention.

[0022] The nuclear power plant (1) includes a reactor (10), a containment vessel (20), a concrete structure (30, reactor building), a support leg (40), a first support structure (50), and a second support structure (60).

[0023] The reactor (10) is a small modular reactor (SMR) that is extended in a first direction and includes a core and a steam generator inside.

[0024] Nuclear power plants using Small Modular Reactors have a structure in which all systems are contained within a reactor vessel assembly without a separate containment building. Consequently, when external seismic loads occur, damage may arise due to collisions between the reactor vessel and the containment vessel, or between the containment vessel and the outer wall of the concrete structure, making the structure relatively vulnerable to seismic loads. The present invention provides safety against external seismic loads for nuclear power plants using Small Modular Reactors.

[0025] The containment vessel (20) surrounds the reactor (10). The space between the reactor (10) and the containment vessel (20) may be a vacuum or filled with gas, though not limited to this. The containment vessel (30) may be made of metal.

[0026] In FIG. 1, the structure for fixing the reactor (10) to the containment vessel (20) is omitted.

[0027] The concrete structure (30) surrounds the containment vessel (20). The reactor (10) may be provided in multiple numbers, and in this case, the concrete structure (30) may also be modified to accommodate multiple reactors (10).

[0028] The support leg (40) connects the lower part of the containment vessel (20) and the bottom surface of the concrete structure (30) and supports the containment vessel (20).

[0029] When an earthquake occurs at the site of a nuclear power plant, the seismic force is transmitted to the concrete structure (30) through the ground beneath the power plant structure, and this seismic force is transmitted to the containment vessel (20) through the support leg (40) and support structure (50, 60), and finally the seismic force is transmitted to the reactor (10).

[0030] The containment vessel (20) is additionally supported on the concrete structure (30) through the first support structure (50) and the second support structure (60), thereby reducing seismic force.

[0031] Referring to FIG. 2, the first support structure (50) will be described in detail.

[0032] The first support structure (50) includes a first support arm (51), a first protruding structure (52), a first support unit (53), and a damping part (54).

[0033] The first support arm (51) is connected to the side wall of the containment vessel (20) and extends onto the concrete structure (30). The extension direction of the first support arm (51) may be horizontal. The first support arm (51) may be made of a steel structure, though not limited thereto. The first support arm (51) may be in the shape of a long, extended rectangular column.

[0034] In another embodiment, the first support arm (51) may extend into the interior of the containment vessel (20) or be coupled to the reactor (10).

[0035] The first protruding structure (52) is extended outward from the concrete structure (30) toward the containment vessel (20). The first protruding structure (52) may be integral with the concrete structure (30) and may be in the shape of a square column.

[0036] The first protruding structure (52) is located on the upper part of the first supporting arm (51), and when viewed from the first direction, the first protruding structure (52) partially overlaps with the first supporting arm (51).

[0037] The first support unit (53) is located in the area where the first protruding structure (52) and the first support arm (51) overlap. The first support unit (53) includes a chain (53a) and a circular seismic spring (53b). The chain (53a) is connected to the first support arm (51), and the circular seismic spring (53b) is connected to the first protruding structure (52). In addition, the first support unit (53) may further include a connecting auxiliary configuration, such as an anchor, to connect the chain (53a) and the circular seismic spring (53b) to the first support arm (51) and the first protruding structure (52), respectively.

[0038] The first support arm (51) is supported by the first support unit (53) in a suspended form on the first protruding structure (52). With this type of support, the gravitational load of the reactor (10) and the containment vessel (20) is stably supported by the chain (53a), and the horizontal and vertical seismic forces transmitted from the concrete structure (30) are significantly reduced.

[0039] The damping section (54) is located between the end of the first support arm (51) and the concrete structure (30). Horizontal displacement that may occur during seismic load is effectively controlled by the damping section (54). A hydraulic damping device may be used as the damping section (54).

[0040] Through this first support structure (50), when an earthquake load occurs, the natural frequency of the containment vessel (20) is shifted from the main frequency of the earthquake load by the chain (53a) and the circular seismic spring (53b) installed on the upper part of the chain (53a), thereby reducing the horizontal and vertical seismic forces, and the lateral amplitude of the containment vessel can be controlled through the damping part (54) installed on the side.

[0041] Referring to FIG. 3, the second support structure (60) will be described in detail.

[0042] The second support structure (60) includes a second support arm (61), a second protruding structure (62), and a second support unit (63).

[0043] The second support arm (61) is connected to the side wall of the containment vessel (20) and extends onto the concrete structure (30). The extension direction of the second support arm (61) may be horizontal. The second support arm (61) may be made of a steel structure, though not limited thereto. The second support arm (61) may be in the shape of a long, extended rectangular column.

[0044] The second support arm (61) may be located at the same height as the first support arm (51), though it is not limited thereto.

[0045] In another embodiment, the second support arm (61) may extend into the interior of the containment vessel (20) or be coupled to the reactor (10).

[0046] The second protruding structure (62) is extended outward from the concrete structure (30) toward the containment vessel (20). The second protruding structure (62) may be integral with the concrete structure (30) and may be in the shape of a square column.

[0047] The second protruding structure (62) is located at the bottom of the second supporting arm (61), and when viewed from the first direction, the second protruding structure (62) partially overlaps with the second supporting arm (61).

[0048] The second support unit (63) is located in the area where the second protruding structure (62) and the second support arm (61) overlap. The second support unit (63) is provided as a seismic isolation device. The seismic isolation device may be a lead-rubber laminate structure. Through the seismic isolation device, the gravitational load of the containment vessel (20) is safely supported, and the horizontal seismic force transmitted from the concrete structure (30) during an earthquake is significantly reduced.

[0049] Referring to FIG. 4, the arrangement relationship between the first support structure (50) and the second support structure (60) is explained.

[0050] The first support structure (50) and the second support structure (60) are provided in multiple numbers and are alternately arranged along the perimeter of the containment vessel (20) on a flat surface. Additionally, the first support structure (50) and the second support structure (60) are arranged at regular intervals.

[0051] According to the present invention, seismic forces can be safely resisted by using a first support structure (50) and a second support structure (60) having different seismic force reduction principles. Alternatively, by reducing vertical and horizontal seismic forces transmitted to the side support of the containment vessel (20), it can contribute to ensuring safety against seismic loads of the reactor (10).

[0052] The support structure (50, 60) according to the present invention can be installed in the following way.

[0053] A second support unit (63) is installed on the upper part of the second protruding structure (62), and a containment container (20) is introduced so that a second support arm (61) is placed on the second support unit (63) and fastened.

[0054] Afterwards, the first support unit (53) is installed between the first support arm (51) and the first protruding structure (52), and tension is introduced.

[0055] Finally, a damping part (54) is installed between the end of the first support arm (51) and the concrete structure (30).

[0056] The aforementioned embodiments are examples for explaining the present invention, and the present invention is not limited thereto. Since a person skilled in the art to which the present invention pertains can implement the present invention by making various modifications therefrom, the technical scope of protection of the present invention should be determined by the appended claims.

Claims

Claim 1 In a nuclear power plant with enhanced safety against earthquakes, the reactor is a small modular reactor having a core and a steam generator arranged inside, and is elongated in a first direction; a containment vessel housing the reactor; and a concrete structure surrounding the containment vessel and spaced apart from the containment vessel. and includes a first support structure for supporting the containment vessel on the concrete structure, wherein the first support structure comprises: a first support arm having one end connected to the containment vessel and the other end protruding toward the concrete structure; a first protruding structure protruding from the concrete structure toward the containment vessel, overlapping at least a portion with the first support arm in the first direction, and positioned on the upper part of the first support arm; a first support unit having one end connected to the first support arm and the other end connected to the first protruding structure, wherein the first support unit comprises a chain, and the first support unit further comprises a circular seismic spring coupled to the chain, and the first support unit further comprises a damping part extending along the first direction, having one end connected to the end of the first support arm and the other end connected to the concrete structure, and further comprises a second support structure for supporting the containment vessel on the concrete structure. A nuclear power plant comprising: a second support structure, wherein one end is connected to the containment vessel and the other end protrudes toward the concrete structure; a second protruding structure protruding from the concrete structure toward the containment vessel, overlapping at least a portion with the second support arm in the first direction, and located at the lower part of the second support arm; and a second support unit, wherein one end contacts the second support arm and the other end contacts the second protruding structure. Claim 2 delete Claim 3 delete Claim 4 A nuclear power plant according to claim 1, wherein the circular seismic spring is connected to the first protruding structure and the chain is connected to the first supporting arm. Claim 5 delete Claim 6 delete Claim 7 In paragraph 1, the second support unit is a seismic isolation unit in a nuclear power plant. Claim 8 In paragraph 7, the first support arm and the second support arm are located at the same height in a nuclear power plant. Claim 9 In claim 8, the first support unit and the second support unit are each provided in multiple numbers and are alternately arranged along the circumference of the containment vessel in a nuclear power plant.

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