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WO2024225583A1 - Récipient de stockage à sec pour combustible nucléaire usé ayant une efficacité de dissipation de chaleur améliorée de la chaleur de désintégration - Google Patents

Récipient de stockage à sec pour combustible nucléaire usé ayant une efficacité de dissipation de chaleur améliorée de la chaleur de désintégration Download PDF

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Publication number
WO2024225583A1
WO2024225583A1 PCT/KR2024/001642 KR2024001642W WO2024225583A1 WO 2024225583 A1 WO2024225583 A1 WO 2024225583A1 KR 2024001642 W KR2024001642 W KR 2024001642W WO 2024225583 A1 WO2024225583 A1 WO 2024225583A1
Authority
WO
WIPO (PCT)
Prior art keywords
nuclear fuel
storage container
spent nuclear
protrusions
dry storage
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
PCT/KR2024/001642
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English (en)
Korean (ko)
Inventor
김승현
강현구
이상환
윤상혁
최윤정
문태철
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Korea Radioactive Waste Agency
Original Assignee
Korea Radioactive Waste Agency
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Korea Radioactive Waste Agency filed Critical Korea Radioactive Waste Agency
Publication of WO2024225583A1 publication Critical patent/WO2024225583A1/fr
Anticipated expiration legal-status Critical
Pending legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008—Containers for fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/06—Details of, or accessories to, the containers
    • G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins

Definitions

  • the present invention relates to a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat, and more specifically, to a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat, which can dissipate heat by highly efficiently transferring heat to a buffer material when a buffer material is installed on an outer surface thereof.
  • Nuclear fuel refers to a material that can be loaded into a nuclear reactor to cause a chain reaction of nuclear fission to produce usable energy
  • spent nuclear fuel refers to the material that remains after electricity has been produced.
  • spent nuclear fuels are ultimately disposed of permanently, and are generally stored in solid rock layers located 500 to 1,000 meters underground.
  • the spent nuclear fuels are placed in a storage container, and then a buffer material is installed around the outer surface of the container so that the buffer material surrounds the outer surface of the container.
  • the buffer material installed on the outer surface of the storage container can surround the outer surface of the storage container to prevent external groundwater, etc. from penetrating into the interior of the storage container, or can perform the function of absorbing radioactive materials leaking from the storage container.
  • the storage container containing the spent nuclear fuel inside may receive a large amount of heat from the spent nuclear fuel and deteriorate, and if the storage container deteriorates and breaks, radioactive materials may leak outside the storage container, causing a serious problem of radioactive contamination of the surrounding environment.
  • One object of the present invention is to provide a dry storage container for spent nuclear fuel capable of effectively dissipating heat generated from spent nuclear fuel.
  • Another object of the present invention is to provide a dry storage container for spent nuclear fuel that can prevent a buffer material installed on an outer surface from being easily separated.
  • a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat may include a container having a lower surface and side surfaces formed at a lower surface and a space formed to accommodate spent nuclear fuel, a lid coupled to an upper surface of the container and capable of sealing the space and including an upper surface, and a plurality of protrusions formed to protrude from at least one surface of the lower surface, the side surfaces, and the upper surface.
  • the plurality of protrusions are formed on the side surface, and the side surface includes a first portion between the lid and a first point spaced a first distance apart in a direction from the lid toward the lower surface, a second portion between the first point and a second point spaced a second distance apart in a direction from the first point toward the lower surface, and a third portion between the second point and the lower surface spaced a third distance apart in a direction from the second point toward the lower surface, and the plurality of protrusions may include a plurality of first protrusions formed to be inclined in a downward direction on the first portion, a plurality of second protrusions formed in a cylindrical shape on the second portion, and a plurality of third protrusions formed to be inclined in an upward direction on the third portion.
  • the second protrusion may be formed on the second portion such that a line segment passing through the center of a cross-section perpendicular to the longitudinal direction of the second protrusion is perpendicular to the side surface.
  • the second distance may be longer than the sum of the first distance and the third distance.
  • the length of the plurality of second protrusions protruding in a vertical direction from the side surface may be longer than the length of the plurality of first protrusions protruding in a vertical direction from the side surface and the length of the plurality of third protrusions protruding in a vertical direction from the side surface.
  • the plurality of third protrusions may each be formed so that the length protruding in the vertical direction from the side increases from the top to the bottom.
  • the plurality of protrusions may include a fourth protrusion formed on the lower surface and a fifth protrusion formed on the upper surface.
  • the fourth protrusion and the fifth protrusion can be formed in a cylindrical shape.
  • the fourth protrusion may be formed such that a line segment passing through the center of a cross-section perpendicular to the longitudinal direction of the fourth protrusion is perpendicular to the lower surface
  • the fifth protrusion may be formed such that a line segment passing through the center of a cross-section perpendicular to the longitudinal direction of the fifth protrusion is perpendicular to the upper surface
  • the dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat provides the effect of effectively dissipating heat transferred from spent nuclear fuel by increasing the area in contact with the buffer material.
  • the buffer material since a plurality of first protrusions are formed so as to be inclined in a downward direction on the upper side of the side of the container, the buffer material provides an effect in which the heat dissipation efficiency of the decay heat can be easily installed in the dry storage container for spent nuclear fuel.
  • FIG. 1 is a drawing illustrating a cross-section of a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat according to one embodiment of the present invention.
  • Figure 2 is an enlarged view of A in Figure 1.
  • Figure 3 is an enlarged view of B in Figure 1.
  • Figure 4 is an enlarged view of C in Figure 1.
  • Figure 5 is an enlarged view of D in Figure 1.
  • Figure 6 is a drawing for explaining and comparing the contact area between the surface of a conventional dry storage container and a buffer material and the contact area between the surface of a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat and a buffer material.
  • FIG. 1 is a drawing illustrating a cross-section of a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat according to one embodiment of the present invention.
  • a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat includes a container (100) and a lid (200).
  • the container (100) includes a lower surface (110) and a side surface (120), and the upper surface is open to form a space (130) inside.
  • the lower surface (110) can be formed in various shapes, and can also be formed in a circular shape.
  • the container (100) can be formed in a cylindrical shape with the lower surface (110) being circular.
  • a plurality of fourth protrusions (112) can be formed on the lower surface (110), and the fourth protrusions (112) can be formed in a cylindrical shape.
  • a plurality of fourth protrusions (112) can be formed on the surface (110) so as to have the largest possible surface area.
  • Figure 2 is an enlarged view of A in Figure 1.
  • the fourth protrusion (112) can be formed so that a line segment (l1) passing through the center of a cross-section perpendicular to the longitudinal direction of the fourth protrusion (112) is perpendicular to the lower surface (110).
  • the side (120) may be formed to extend upward from the lower surface (110), and when the container (100) is formed in a cylindrical shape, the cross-section parallel to the lower surface (110) may be formed to be annular.
  • a plurality of protrusions can be formed on the side (120).
  • a plurality of first protrusions (122-1) may be formed on a first portion between the lid (200) and a first point (a) spaced apart from the lid (200) by a first distance (d1) in a direction toward the lower surface (110) on the side surface (120).
  • a plurality of first protrusions (122-1) can be formed to be inclined in a downward direction.
  • a buffer material (2) such as bentonite, which is installed in a downward direction from the top of the dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat, can be easily placed on the dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat.
  • a plurality of second protrusions (124-1) may be formed on the second portion between the first point (a) and the second point (b) spaced apart from the first point (a) by a second distance (d2) in the direction toward the lower surface (110) on the side surface (120).
  • a plurality of second protrusions (124-1) may be formed in a cylindrical shape, and when the second protrusions (124-1) are formed in a cylindrical shape, the plurality of second protrusions (124-1) may be formed on the side surface (120) so as to have the widest possible surface area.
  • Figure 3 is an enlarged view of B in Figure 1.
  • the second protrusion (124-1) may be formed in the second portion such that a line segment (l2) passing through the center of a cross-section perpendicular to the longitudinal direction of the second protrusion (124-1) is perpendicular to the side surface (120).
  • a plurality of third protrusions (126-1) may be formed on the side surface (120) in a third portion between the second point (b) and the lower surface (110) spaced apart from the second point (b) by a third distance (d3) in the direction toward the lower surface (110).
  • Figure 4 is an enlarged view of C in Figure 1.
  • a plurality of third protrusions (126-1) may be formed to be inclined in an upward direction, and as shown in FIG. 4, each may be formed so that the length protruding in the vertical direction from the side (120) becomes longer as it goes from the top to the bottom.
  • the buffer material (2) installed in the dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat can be prevented from being easily separated from the dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat by being caught by the plurality of third protrusions (126-1).
  • the plurality of protrusions formed on the side (120) can be formed so that the area in contact with the buffer material (2) is as large as possible so as to efficiently transfer heat to the buffer material (2).
  • the second protrusion (124-1) formed in a cylindrical shape can be formed to have a larger surface area than the first protrusion (122-1) or the third protrusion (126-1), the second protrusion (124-1) can be formed on the side (120) to occupy a relatively larger volume than the first protrusion (122-1) or the third protrusion (126-1).
  • the second distance (d2) which is the length of the second portion where the second protrusion (124-1) is formed, may be formed longer than the sum of the first distance (d1), which is the length of the first portion where the first protrusion (122-1) is formed, and the third distance (d3), which is the length of the third portion where the third protrusion (126-1) is formed.
  • a plurality of protrusions may be formed so that the length of the plurality of second protrusions (124-1) protruding in a vertical direction from the side surface (120) is longer than the length of the plurality of first protrusions (122-1) protruding in a vertical direction from the side surface (120) and the length of the plurality of third protrusions (126-1) protruding in a vertical direction from the side surface (120).
  • the space (130) of the container (100) is formed so as to be able to accommodate spent nuclear fuel therein.
  • the lid (200) is attached to the upper part of the container (100) to seal the space (130) and includes an upper surface (210).
  • the lid (200) can be formed in various shapes, and when the container (100) is formed in a cylindrical shape, the lid (200) can also be formed in a circular plate shape.
  • a plurality of fifth protrusions (212) may be formed on the upper surface (210) of the lid (200), and the fifth protrusions (212) may be formed in a cylindrical shape.
  • a plurality of fifth protrusions (212) can be formed on the upper surface (210) so as to have the largest possible surface area.
  • Figure 5 is an enlarged view of D in Figure 1.
  • the fifth protrusion (212) may be formed such that a line segment (l3) passing through the center of a cross-section perpendicular to the longitudinal direction of the fifth protrusion (212) is perpendicular to the upper surface (210).
  • a buffer material (2) is installed in a dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat containing spent nuclear fuel in the internal space (130).
  • the buffer material (2) is installed by covering the spent nuclear fuel dry storage container (1) with improved heat dissipation efficiency from decay heat in a direction from the top to the bottom.
  • the buffer material (2) can be easily placed on the spent nuclear fuel dry storage container (1) with improved heat dissipation efficiency of decay heat.
  • the buffer material (2) installed to surround the outer surface of the dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat is effectively prevented from being separated from the dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat by being caught by a plurality of third protrusions (126-1) formed to be inclined in an upward direction.
  • the contact area between the dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat and the buffer material (2) is increased, so that the heat dissipation efficiency of the heat transferred from the spent nuclear fuel of the dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat is improved.
  • Figure 6 is a drawing for explaining and comparing the contact area between the surface of a conventional dry storage container and a buffer material and the contact area between the surface of a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat and a buffer material.
  • the contact area between the dry storage container (1) for spent nuclear fuel and the buffer material (2) with improved heat dissipation efficiency of decay heat becomes larger than the contact area between the conventional dry storage container (3) and the buffer material (2) in which no protrusions are formed on the outer surface (see FIG. 6 (a)).
  • a dry storage container (1) for spent nuclear fuel with improved heat dissipation efficiency of decay heat which has a larger contact area with the buffer (2) than a conventional dry storage container (3), can transfer heat to the buffer (2) with higher efficiency and dissipate the heat.
  • the dry storage container for spent nuclear fuel with improved heat dissipation efficiency provides the effect of effectively dissipating heat transferred from the spent nuclear fuel by increasing the area in contact with the buffer material.
  • the buffer material since a plurality of first protrusions are formed so as to be inclined in a downward direction on the upper side of the side of the container, the buffer material provides an effect in which the heat dissipation efficiency of the decay heat can be easily installed in the dry storage container for spent nuclear fuel.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Buffer Packaging (AREA)
  • Details Of Rigid Or Semi-Rigid Containers (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)

Abstract

La présente invention concerne un récipient de stockage à sec pour combustible nucléaire usé avec une efficacité de dissipation de chaleur améliorée de la chaleur de désintégration. Le récipient de stockage à sec pour combustible nucléaire usé avec une efficacité de dissipation de chaleur améliorée de la chaleur de désintégration a une pluralité de saillies formées sur la surface externe de celui-ci et peut ainsi transférer de la chaleur avec une efficacité élevée à un matériau tampon installé sur la surface externe de celui-ci.
PCT/KR2024/001642 2023-04-27 2024-02-05 Récipient de stockage à sec pour combustible nucléaire usé ayant une efficacité de dissipation de chaleur améliorée de la chaleur de désintégration Pending WO2024225583A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
KR10-2023-0055350 2023-04-27
KR1020230055350A KR102615120B1 (ko) 2023-04-27 2023-04-27 붕괴열의 방열 효율이 향상된 사용후핵연료 건식 저장 용기

Publications (1)

Publication Number Publication Date
WO2024225583A1 true WO2024225583A1 (fr) 2024-10-31

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PCT/KR2024/001642 Pending WO2024225583A1 (fr) 2023-04-27 2024-02-05 Récipient de stockage à sec pour combustible nucléaire usé ayant une efficacité de dissipation de chaleur améliorée de la chaleur de désintégration

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WO (1) WO2024225583A1 (fr)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR102615120B1 (ko) * 2023-04-27 2023-12-19 한국원자력환경공단 붕괴열의 방열 효율이 향상된 사용후핵연료 건식 저장 용기
KR102764134B1 (ko) 2024-08-19 2025-02-07 한국원자력환경공단 내부압력 저감 구조를 갖는 사용후핵연료 저장 용기

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0968594A (ja) * 1995-08-31 1997-03-11 Ishikawajima Harima Heavy Ind Co Ltd 放射性廃棄物保管処分用容器
JP2013029521A (ja) * 2012-09-28 2013-02-07 Toshiba Corp 放射性廃棄物収納容器除熱構造
KR20140082104A (ko) * 2012-12-21 2014-07-02 주식회사 포스코 핵연료봉 저장 캐스크
KR20180067545A (ko) * 2015-10-16 2018-06-20 티엔 인터내셔날 패키지로부터 열을 방출하기 위한 베이스를 가진 냉각 요소
JP2019152555A (ja) * 2018-03-05 2019-09-12 株式会社東芝 使用済核燃料の支持構造物、支持構造物の製造方法及び使用済核燃料容器
KR102615120B1 (ko) * 2023-04-27 2023-12-19 한국원자력환경공단 붕괴열의 방열 효율이 향상된 사용후핵연료 건식 저장 용기

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010175331A (ja) * 2009-01-28 2010-08-12 Toshiba Corp 放射性廃棄物収納容器除熱構造

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0968594A (ja) * 1995-08-31 1997-03-11 Ishikawajima Harima Heavy Ind Co Ltd 放射性廃棄物保管処分用容器
JP2013029521A (ja) * 2012-09-28 2013-02-07 Toshiba Corp 放射性廃棄物収納容器除熱構造
KR20140082104A (ko) * 2012-12-21 2014-07-02 주식회사 포스코 핵연료봉 저장 캐스크
KR20180067545A (ko) * 2015-10-16 2018-06-20 티엔 인터내셔날 패키지로부터 열을 방출하기 위한 베이스를 가진 냉각 요소
JP2019152555A (ja) * 2018-03-05 2019-09-12 株式会社東芝 使用済核燃料の支持構造物、支持構造物の製造方法及び使用済核燃料容器
KR102615120B1 (ko) * 2023-04-27 2023-12-19 한국원자력환경공단 붕괴열의 방열 효율이 향상된 사용후핵연료 건식 저장 용기

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