WO2013024994A2 - Apparatus for treating molten atomic reactor fuel rod using vertical cavity - Google Patents

Apparatus for treating molten atomic reactor fuel rod using vertical cavity Download PDF

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Publication number
WO2013024994A2
WO2013024994A2 PCT/KR2012/006146 KR2012006146W WO2013024994A2 WO 2013024994 A2 WO2013024994 A2 WO 2013024994A2 KR 2012006146 W KR2012006146 W KR 2012006146W WO 2013024994 A2 WO2013024994 A2 WO 2013024994A2
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Prior art keywords
reactor
vertical cavity
molten
fuel rods
fuel rod
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PCT/KR2012/006146
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French (fr)
Korean (ko)
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WO2013024994A3 (en
Inventor
한만엽
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주식회사 아앤시티
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Priority claimed from KR1020110096313A external-priority patent/KR101278196B1/en
Application filed by 주식회사 아앤시티 filed Critical 주식회사 아앤시티
Priority to CN201280039502.4A priority Critical patent/CN103733266B/en
Publication of WO2013024994A2 publication Critical patent/WO2013024994A2/en
Publication of WO2013024994A3 publication Critical patent/WO2013024994A3/en

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/016—Core catchers
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the core cooling function of the reactor is lost due to an accident and abnormal operation of the reactor, the fuel rod of the reactor is melted, and the internal containment vessel is broken, and a serious accident in which the molten nuclear fuel is discharged to the outside occurs.
  • the present invention relates to an apparatus for automatically treating molten fuel rods without the operation of human or personnel to block or minimize radioactive leakage.
  • a nuclear power plant is divided into a nuclear steam supply system centered on a reactor, a turbine and generator system that receives steam, and runs a generator.
  • the reactor is a device having a function to convert the nuclear energy into electrical energy by controlling so that a large amount of energy released during the nuclear reaction is gradually released.
  • FIG. 1 shows a reactor of such a nuclear power plant and a containment vessel that isolates it from the outside.
  • the inner containment vessel 1 of the nuclear reactor is isolated from the external environment by the primary partition 2, the secondary partition 4, and the containment building 3.
  • heated steam operates the steam turbine outside the reactor, and the cooled steam has a closed cooling water circulation structure that flows back into the inner containment vessel.
  • a fuel rod 6 is disposed below the conventional internal containment vessel 1, and when the sudden change or accident of the external environment occurs, all the stabilizers of the reactor malfunction and become impossible to control. May rise sharply. In this case, the fuel rods 6 are melted to release the fuel rods melted out of the reactor containment vessel, and the molten fuel rods melt the concrete structure and the ground under the reactor and contaminate groundwater flowing through the surrounding soil and joint. May result.
  • the core cooling function of the reactor is lost due to an accident and abnormal operation of the reactor, the fuel rod of the reactor is melted, and the internal containment vessel is broken, and a serious accident in which the molten nuclear fuel is discharged to the outside occurs.
  • a device that automatically cools molten fuel rods over a long period of time in a containment building and blocks or minimizes radiation leakage by reducing energy by allowing aggregates or concrete installed inside to react with the molten fuel rods automatically without the use of fire or personnel. will be.
  • the present invention provides an apparatus for treating a molten reactor fuel rods comprising a device for blocking the flow of groundwater by grouting the joint or joint of the lower part of the reactor.
  • it may further include an order wall surrounding the reactor to block the flow of groundwater located below the reactor.
  • it may further include a slab located below the reactor and a vertical cavity formed downward from the slab.
  • it may further include one or more blocking blocks disposed above the vertical cavity.
  • the present invention may further include a brace cover or a waterproof cover covering the vertical cavity to stop the blocking block.
  • the blocking block may move to seal the vertical cavity when the brace cover or the waterproof cover is removed.
  • it may further include a concrete placing pipe for introducing concrete from the outside to the upper vertical cavity.
  • the core cooling function of the reactor is lost due to an accident and abnormal operation of the reactor, the fuel rod of the reactor is melted, and the internal containment vessel is broken, and a serious accident in which the molten nuclear fuel is discharged to the outside occurs. It reduces the energy by allowing aggregates and concrete installed inside to react with the molten fuel rods automatically without the operation of manpower or manpower, and gradually cools the molten fuel rods by burying them in the cavity formed in the underground rock below the nuclear power plant. Can be exercised.
  • the present invention can prevent groundwater from being contaminated by radioactivity by grouting joints and joints and by installing underground order walls.
  • the present invention by injecting concrete into the concrete pouring pipe connected to the inner storage container surrounding the interior, it can be completely isolated from the outside to prevent the radiation is emitted to the surroundings.
  • FIG. 1 is a cross-sectional view of a reactor of a conventional nuclear power plant and a containment vessel that isolates it from the outside.
  • FIG. 2 is a cross-sectional view of an apparatus for processing a molten reactor fuel rod of the present invention.
  • FIG 3 is a cross-sectional view around the reactor of another embodiment of an apparatus for processing molten reactor fuel rods of the present invention.
  • FIG. 4 is a cross-sectional view around the reactor of another embodiment of an apparatus for processing molten reactor fuel rods of the present invention.
  • FIG. 5 is a schematic diagram illustrating operation of an apparatus for processing fuel rods of a molten reactor of the present invention.
  • FIG. 2 shows the overall structure of an apparatus for treating molten reactor fuel rods of the present invention.
  • an inner circumference of the inner storage container 1 is formed with a primary partition 2 and a containment building 3 provided with a secondary partition 4.
  • the partition 2 is supported by the foundation slab 8.
  • An opening is formed in the lower surface of the primary partition wall 2, and a vertical cavity 11 for embedding the molten fuel rod is formed in the foundation slab 8 supporting the primary partition wall 2.
  • the vertical cavity 11 is formed up to a rock located in the basement, when the fuel rod 6 melts due to a serious accident and falls from the internal containment vessel 1, the vertical cavity 11 falls into the vertical cavity 11. .
  • the molten fuel rod 6 reacts with the rock to reduce the heat of reaction and isolate from the outside to block the outflow of radioactivity.
  • the melting target material 15 is stacked in the vertical cavity 11.
  • the apparatus further includes a device that blocks groundwater flow by grouting the joint or joint around the vertical cavity 11 to prevent groundwater flowing along the joint or joint, thereby preventing contamination of the groundwater with radiation. .
  • the waterproof cover 14, the block brace cover 12, the waterproof cover 14 and the block brace cover (under the lower portion of the inner containment container (1) And a blocking block 13 supported by 12).
  • Such blocking blocks may be two as shown in FIG. 3 or a plurality as shown in FIG. 4.
  • the blocking block 13 is disposed on the lower side of the inner storage container 1, and is disposed on a circular support member disposed on the foundation slab as shown in Figs.
  • the blocking block 13 is made of a material capable of shielding radiation, such as concrete, lead, or polymer hydrocarbon, and the supporting member may be polygonal as well as circular, and supports the edge of the blocking block 13.
  • two blocking blocks 13 are supported by the waterproof cover 14 and the block brace cover 12, or as shown in FIG. 4, one blocking block 13. It is supported by the waterproof cover 14 and the block brace cover 12 from the opposite wall.
  • the blocking block 13 is rotated by the center of gravity when the supporting structure, that is, the waterproof cover 14 and the block brace cover 12 is removed, thereby blocking the vertical cavity 11.
  • the concrete pouring pipe 30 is connected to the cavity 7, and the concrete pouring pipe 30 may introduce concrete into the cavity 7 by an external pump 31.
  • Such concrete pouring pipe 30 may be changed as necessary in various forms other than the form shown in the drawings.
  • 5 illustrates a method of operation of an apparatus for treating molten reactor fuel rods of the present invention.
  • 5 (a) to (e) is a process of embedding the molten fuel rod 6 in the vertical cavity 11 installed in the surrounding rock of the lower part of the reactor when the molten fuel rod 6 is separated from the internal containment vessel 1 according to the present invention To show.
  • FIG. 5A illustrates a process in which the molten fuel rod 6 is separated from the inner containment vessel 1 and falls into the waterproof cover 14 to melt the waterproof cover 14.
  • the hot fuel rod 6 separated by the malfunction of the inner containment container 1 is melted in contact with the waterproof cover 14, it is dropped between the two support blocks 13 and the support block cover ( 12) are stacked on.
  • the dropped fuel rod 6 melts the block prop cover 12 and falls into the vertical cavity 11 in which the melting target material 15 is stored.
  • the molten fuel rods 6 fall into the vertical cavity 11 and are stacked, and then the heat of reaction of the molten fuel rods 6 is consumed to melt the material to be melted. do.
  • the bracing block cover 12 is broken so that the two blocking blocks 13 that can no longer support each other are rotated toward the center.
  • the apparatus for processing the molten reactor fuel rod using the vertical cavity loses the core cooling function of the reactor due to an accident and abnormal operation of the reactor, and the internal containment vessel is broken after the fuel rod of the reactor melts, In the event of a serious accident in which the spent nuclear fuel is released to the outside, aggregates or concrete, etc. installed inside the reactor react with the molten fuel rods automatically without power or manpower to reduce the energy. By embedding in the formed cavity, it is possible to exert the effect of gradually cooling the molten fuel rod over a long period of time.
  • the present invention can prevent groundwater from being contaminated by radiation by grouting joints and joints and installing underground order walls.
  • the present invention by injecting concrete into the concrete pouring pipe connected to the inner storage container surrounding the interior, it can be completely isolated from the outside to prevent radiation to be emitted to the surroundings.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The present invention relates to an apparatus for blocking or minimizing radiation leakage by automatically treating molten fuel rods, without power or human effort, when a major accident occurs due to a malfunction of an atomic reactor that leads to melting/damaging of fuel rod containers inside the atomic reactor after the fuel rods, which are used in the atomic reactor, become molten.

Description

수직공동을 이용한 용융된 원자로 연료봉을 처리하는 장치A device for processing molten reactor fuel rods using vertical cavities
본 발명은 사고 및 원자로의 비정상적인 가동 등에 의하여 원자로의 노심 냉각기능이 상실되고 원자로의 연료봉이 용융된 후 내부 격납용기가 파손되어, 용융된 핵 연료가 외부로 방출되는 중대사고가 발생되었을 경우, 동력이나 인력의 작동없이 자동적으로 용융된 연료봉을 처리하여, 방사능 유출을 차단하거나 최소화하는 장치에 관한 것이다.In the present invention, the core cooling function of the reactor is lost due to an accident and abnormal operation of the reactor, the fuel rod of the reactor is melted, and the internal containment vessel is broken, and a serious accident in which the molten nuclear fuel is discharged to the outside occurs. The present invention relates to an apparatus for automatically treating molten fuel rods without the operation of human or personnel to block or minimize radioactive leakage.
일반적으로 원자력 발전소는 원자로를 중심으로 한 핵증기 공급 계통과 증기를 공급받아 발전기를 돌리는 터빈·발전기 계통 그리고 기타 부수설비로 구분된다. 여기서, 원자로는 핵 반응시 방출되는 다량의 에너지가 서서히 방출되도록 조절함으로써 핵에너지를 전기 에너지로 전환할 수 있도록 하는 기능을 갖는 장치이다.In general, a nuclear power plant is divided into a nuclear steam supply system centered on a reactor, a turbine and generator system that receives steam, and runs a generator. Here, the reactor is a device having a function to convert the nuclear energy into electrical energy by controlling so that a large amount of energy released during the nuclear reaction is gradually released.
도 1 은 이러한 원자력 발전소의 원자로와 이를 외부와 격리시키는 격납용기 를 도시한다. 도 1 에 도시된 바와 같이, 원자로의 내부 격납용기(1)는 1차 격벽(2), 2차 격벽(4), 및 격납건물(3) 에 의하여 외부 환경과 격리되어 있고, 내부 격납용기(1)와 외부 터빈 사이에는 가열된 증기가 원자로 외부의 증기터빈을 가동시키고, 냉각된 증기는 다시 내부 격납용기로 유입되는 폐쇄형 냉각수 순환 구조를 하고 있다.1 shows a reactor of such a nuclear power plant and a containment vessel that isolates it from the outside. As shown in FIG. 1, the inner containment vessel 1 of the nuclear reactor is isolated from the external environment by the primary partition 2, the secondary partition 4, and the containment building 3. Between 1) and the external turbine, heated steam operates the steam turbine outside the reactor, and the cooled steam has a closed cooling water circulation structure that flows back into the inner containment vessel.
상기 종래의 내부 격납용기(1)의 하부에는 연료봉(6)이 배치되어 있으며, 외부 환경의 급격한 변화 혹은 사고가 발생하여 원자로의 안정장치가 모두 오작동을 하고 제어가 불가능하게 되면, 원자로 내부의 온도가 급격히 상승할 수 있다. 이 경우, 연료봉(6)이 용융되어 원자로 격납용기 외부로 용융된 연료봉이 방출되고, 이러한 용융된 연료봉이 원자로 하부의 콘크리트 구조물 및 지반을 용융시켜, 주변 토양 및 절리를 통해 흐르는 지하수를 오염시키는 상황을 초래할 수 있다.A fuel rod 6 is disposed below the conventional internal containment vessel 1, and when the sudden change or accident of the external environment occurs, all the stabilizers of the reactor malfunction and become impossible to control. May rise sharply. In this case, the fuel rods 6 are melted to release the fuel rods melted out of the reactor containment vessel, and the molten fuel rods melt the concrete structure and the ground under the reactor and contaminate groundwater flowing through the surrounding soil and joint. May result.
따라서, 이러한 연료봉(6)의 용융물을 억류시키고 냉각시키는 장치 및 그 방법이 연구되고 있다. 종래에 고온의 연료봉 용융물과 냉각수를 직접 반응시키는 냉각장치가 제안된 바 있으나, 이 방법은 밀폐된 공간에서 고온의 용융물과 냉각수가 직접 반응함으로써 급격한 증기 생성을 초래하여 증기폭발이 발생할 수 있는 문제점이 있으며, 냉각시킬 수 있는 양에 한계가 있고, 증기의 확산 현상에 의해 2차 문제도 발생할 수 있다.Therefore, an apparatus and method for detaining and cooling the melt of the fuel rod 6 have been studied. Conventionally, a cooling device for directly reacting a high temperature fuel rod melt and a cooling water has been proposed, but this method has a problem in that a vapor explosion may occur due to rapid steam generation by directly reacting a high temperature melt and a cooling water in a closed space. In addition, there is a limit to the amount that can be cooled, secondary problems may also occur due to the diffusion of steam.
따라서 상기와 같은 문제를 방지할 수 있는 용융된 연료봉의 안전한 처리가 요구된다.Therefore, a safe treatment of the molten fuel rods that can prevent the above problems is required.
본 발명은 사고 및 원자로의 비정상적인 가동 등에 의하여 원자로의 노심 냉각기능이 상실되고 원자로의 연료봉이 용융된 후 내부 격납용기가 파손되어, 용융된 핵 연료가 외부로 방출되는 중대사고가 발생되었을 경우, 동력이나 인력의 작동없이 자동적으로 내부에 설치된 골재나 콘크리트 등이 용융된 연료봉과 반응하도록 하여 에너지를 감소시킴으로서 격납 건물 내에서 장기간에 걸쳐 용융된 연료봉을 서서히 냉각시키고 방사능 유출을 차단하거나 최소화하는 장치에 관한 것이다.In the present invention, the core cooling function of the reactor is lost due to an accident and abnormal operation of the reactor, the fuel rod of the reactor is melted, and the internal containment vessel is broken, and a serious accident in which the molten nuclear fuel is discharged to the outside occurs. A device that automatically cools molten fuel rods over a long period of time in a containment building and blocks or minimizes radiation leakage by reducing energy by allowing aggregates or concrete installed inside to react with the molten fuel rods automatically without the use of fire or personnel. will be.
상기와 같은 과제를 해결하기 위하여, 본 발명은 원자로 하부의 절리 혹은 조인트를 그라우팅하여 지하수의 흐름을 차단하는 장치를 포함하는 용융된 원자로 연료봉을 처리하는 장치를 제공한다.In order to solve the above problems, the present invention provides an apparatus for treating a molten reactor fuel rods comprising a device for blocking the flow of groundwater by grouting the joint or joint of the lower part of the reactor.
본 발명에서는, 상기 원자로 하부에 위치하는 지하수 흐름을 차단하는, 상기 원자로를 둘러싸는 차수벽을 더 포함할 수도 있다.In the present invention, it may further include an order wall surrounding the reactor to block the flow of groundwater located below the reactor.
본 발명에서는, 원자로 하부에 위치하는 슬래브 및 상기 슬래브로부터 하측으로 형성된 수직공동을 더 포함할 수도 있다. In the present invention, it may further include a slab located below the reactor and a vertical cavity formed downward from the slab.
본 발명에서는, 상기 수직공동의 상부에 배치되는 한 개 이상의 차단블럭을 더 포함할 수도 있다.In the present invention, it may further include one or more blocking blocks disposed above the vertical cavity.
본 발명에서는, 상기 차단 블록을 정지시키는, 상기 수직공동을 덮는 버팀 덮개 또는 방수 덮개를 더 포함할 수도 있다.The present invention may further include a brace cover or a waterproof cover covering the vertical cavity to stop the blocking block.
본 발명에서는, 상기 차단블럭은 상기 버팀 덮개 또는 방수 덮개가 제거되는 경우, 상기 수직공동을 밀폐시키도록 이동할 수도 있다. In the present invention, the blocking block may move to seal the vertical cavity when the brace cover or the waterproof cover is removed.
본 발명에서는, 외부로부터 콘크리트를 상기 수직공동 상부로 유입시킬 수 있는 콘크리트 타설용관을 더 포함할 수도 있다.In the present invention, it may further include a concrete placing pipe for introducing concrete from the outside to the upper vertical cavity.
본 발명은 사고 및 원자로의 비정상적인 가동 등에 의하여 원자로의 노심 냉각기능이 상실되고 원자로의 연료봉이 용융된 후 내부 격납용기가 파손되어, 용융된 핵 연료가 외부로 방출되는 중대사고가 발생되었을 경우, 동력이나 인력의 작동없이 자동적으로 내부에 설치된 골재나 콘크리트 등이 용융된 연료봉과 반응하도록 하여 에너지를 감소시키고 원자력 발전소 하부의 지하 암반에 형성된 공동에 매립함으로써 장기간에 걸쳐 용융된 연료봉을 서서히 냉각시키는 효과를 발휘할 수 있다.In the present invention, the core cooling function of the reactor is lost due to an accident and abnormal operation of the reactor, the fuel rod of the reactor is melted, and the internal containment vessel is broken, and a serious accident in which the molten nuclear fuel is discharged to the outside occurs. It reduces the energy by allowing aggregates and concrete installed inside to react with the molten fuel rods automatically without the operation of manpower or manpower, and gradually cools the molten fuel rods by burying them in the cavity formed in the underground rock below the nuclear power plant. Can be exercised.
또한, 본 발명은 절리와 조인트를 그라우팅하고 지하 차수벽을 설치함으로써 지하수가 방사능에 오염되는 것을 방지할 수 있다.In addition, the present invention can prevent groundwater from being contaminated by radioactivity by grouting joints and joints and by installing underground order walls.
또한, 본 발명은 내부 격납용기 주변에 연결된 콘크리트 타설용관으로 콘크리트를 주입시켜 내부에 콘크리트를 타설함으로써, 외부와 완전히 격리하여 주변으로 방사선이 방출되는 것을 방지할 수 있다.In addition, the present invention by injecting concrete into the concrete pouring pipe connected to the inner storage container surrounding the interior, it can be completely isolated from the outside to prevent the radiation is emitted to the surroundings.
도 1 은 종래의 원자력 발전소의 원자로와 이를 외부와 격리시키는 격납용기의 단면도.1 is a cross-sectional view of a reactor of a conventional nuclear power plant and a containment vessel that isolates it from the outside.
도 2 는 본 발명의 용융된 원자로 연료봉을 처리하는 장치의 단면도.2 is a cross-sectional view of an apparatus for processing a molten reactor fuel rod of the present invention.
도 3 은 본 발명의 용융된 원자로 연료봉을 처리하는 장치의 다른 실시예의 원자로 주변의 단면도.3 is a cross-sectional view around the reactor of another embodiment of an apparatus for processing molten reactor fuel rods of the present invention.
도 4 는 본 발명의 용융된 원자로 연료봉을 처리하는 장치의 다른 실시예의 원자로 주변의 단면도.4 is a cross-sectional view around the reactor of another embodiment of an apparatus for processing molten reactor fuel rods of the present invention.
도 5 는 본 발명의 용융된 원자로의 연료봉을 처리하는 장치의 작동을 나타내는 개략도.5 is a schematic diagram illustrating operation of an apparatus for processing fuel rods of a molten reactor of the present invention.
이하, 본 발명이 속하는 기술분야에서 통상의 지식을 가진 자가 본 발명을 용이하게 실시할 수 있을 정도로 설명하기 위하여 본 발명의 가장 바람직한 실시예를 첨부된 도면을 참조하여 설명하기로 한다.DETAILED DESCRIPTION Hereinafter, exemplary embodiments of the present invention will be described with reference to the accompanying drawings so that those skilled in the art can easily implement the present invention.
도 2 은 본 발명의 용융된 원자로 연료봉을 처리하는 장치의 전체적인 구조를 도시한다. 도 2 에 도시된 바와 같이, 본 발명의 장치에서는 내부 격납용기(1) 외부 둘레에는 1차 격벽(2)과, 2차 격벽(4)이 설치된 격납건물(3)이 형성되어 있고, 1차 격벽(2)은 기초슬래브(8)에 의하여 지지된다. 2 shows the overall structure of an apparatus for treating molten reactor fuel rods of the present invention. As shown in FIG. 2, in the apparatus of the present invention, an inner circumference of the inner storage container 1 is formed with a primary partition 2 and a containment building 3 provided with a secondary partition 4. The partition 2 is supported by the foundation slab 8.
1차 격벽(2)의 하면에는 개구부가 형성되어 있고, 상기 1차 격벽(2)을 지지하는 기초슬래브(8)에는 용융된 연료봉을 매립하기 위한 수직공동(11)이 길게 형성되어 있다.An opening is formed in the lower surface of the primary partition wall 2, and a vertical cavity 11 for embedding the molten fuel rod is formed in the foundation slab 8 supporting the primary partition wall 2.
이러한 수직공동(11)은 지하에 위치하는 암반까지 형성되어 있기 때문에, 중대발생 사고로 연료봉(6)이 용융되어, 내부 격납용기(1)로부터 낙하하는 경우, 수직공동(11) 내로 낙하하게 된다. 이 경우, 상기 수직공동은 암반에 둘러싸여 있기 때문에, 용융된 연료봉(6)이 암반과 반응하여 반응열이 감소하고, 외부로부터 격리함으로써 방사능의 유출을 차단한다.Since the vertical cavity 11 is formed up to a rock located in the basement, when the fuel rod 6 melts due to a serious accident and falls from the internal containment vessel 1, the vertical cavity 11 falls into the vertical cavity 11. . In this case, since the vertical cavity is surrounded by the rock, the molten fuel rod 6 reacts with the rock to reduce the heat of reaction and isolate from the outside to block the outflow of radioactivity.
바람직하게는 상기 수직공동(11)에는 용융대상물질(15)이 적층되어 있다.Preferably, the melting target material 15 is stacked in the vertical cavity 11.
더욱 바람직하게는 상기 수직공동(11) 주변의 절리 혹은 조인트를 그라우팅(200)하여 지하수의 흐름을 차단하는 장치를 더 포함함으로써, 절리 혹은 조인트를 따라 흐르는 지하수가 방사능에 오염되는 것을 방지할 수 있다.More preferably, the apparatus further includes a device that blocks groundwater flow by grouting the joint or joint around the vertical cavity 11 to prevent groundwater flowing along the joint or joint, thereby preventing contamination of the groundwater with radiation. .
더욱 바람직하게는, 상기 수직공동 주변의 지하수 흐름을 차단하는, 상기 수직공동을 둘러싸는 차수벽(100)을 더 포함함으로써, 상기와 같은 효과를 더욱 확실하게 발휘할 수 있다.More preferably, by further including an order wall 100 surrounding the vertical cavity, which blocks groundwater flow around the vertical cavity, the above effects can be more reliably exhibited.
본 발명의 다른 실시예에서는 도 3 및 도 4 에 도시된 바와 같이 내부 격납용기(1)의 하부에 방수덮개(14), 블록 버팀 덮개(12), 상기 방수덮개(14)와 블록버팀덮개(12)에 의하여 지지되는 차단블록(13)을 포함한다. 이러한 차단블록은 도 3에 도시된 바와 같이 2 개이거나 도 4에 도시된 바와 같이 1개 등 다수개일 수도 있다.In another embodiment of the present invention, as shown in Figures 3 and 4, the waterproof cover 14, the block brace cover 12, the waterproof cover 14 and the block brace cover (under the lower portion of the inner containment container (1) And a blocking block 13 supported by 12). Such blocking blocks may be two as shown in FIG. 3 or a plurality as shown in FIG. 4.
상기 차단블록(13)은 내부 격납용기(1)의 하측에 배치되어 있고, 도 3, 4 에 도시된 바와 같이 기초 슬래브상에 배치된 원 형상의 지지부재 위에 배치되어 있다. 차단블록(13)은 콘크리트, 납, 혹은 고분자 탄화수소와 같이 방사선을 차폐할 수 있는 물질로 구성되며, 지지부재는 원 형상 뿐만아니라 다각형 형상일 수 있으며 차단블록(13)의 가장자리를 지지한다. 정상적으로 원자로가 작동할 때에는 도 3 에서와 같이 두 개의 차단블록(13)은 방수덮개(14) 및 블록 버팀 덮개(12)에 의하여 지지되어 있거나 혹은 도 4에서와 같이, 하나의 차단블록(13)이 이에 마주보는 벽으로부터 방수덮개(14) 및 블록 버팀 덮개(12)에 의하여 지지되어 있다. The blocking block 13 is disposed on the lower side of the inner storage container 1, and is disposed on a circular support member disposed on the foundation slab as shown in Figs. The blocking block 13 is made of a material capable of shielding radiation, such as concrete, lead, or polymer hydrocarbon, and the supporting member may be polygonal as well as circular, and supports the edge of the blocking block 13. When the reactor is operating normally, as shown in FIG. 3, two blocking blocks 13 are supported by the waterproof cover 14 and the block brace cover 12, or as shown in FIG. 4, one blocking block 13. It is supported by the waterproof cover 14 and the block brace cover 12 from the opposite wall.
이와 같은 구성에서 차단블록(13)은 지지하는 구조물, 즉 방수덮개(14) 및 블록 버팀 덮개(12)가 제거되면 무게중심에 의하여 회전하게 되고, 결과적으로 상기 수직공동(11)을 막는다.In such a configuration, the blocking block 13 is rotated by the center of gravity when the supporting structure, that is, the waterproof cover 14 and the block brace cover 12 is removed, thereby blocking the vertical cavity 11.
즉, 용융된 연료봉(6)이 방수덮개(14)를 녹이고 떨어지면, 이차적으로 용융된 원료봉(6)은 블록 버팀 덮개(12)를 용융시켜 제거한 후에 수직공동(11)로 낙하한다.That is, when the molten fuel rod 6 melts and falls off the waterproof cover 14, the secondary molten raw material rod 6 falls into the vertical cavity 11 after melting and removing the block prop cover 12.
한편, 공동(7)에는 콘크리트 타설용관(30)이 연결되어 있고, 콘크리트 타설용관(30)은 외부의 펌프(31)에 의하여 콘크리트를 공동(7)으로 유입시킬 수 있다. 이러한 콘크리트 타설용관(30)은 도면에 도시된 형태 이외의 다양한 형태로 필요에 따라 변경될 수 있다. Meanwhile, the concrete pouring pipe 30 is connected to the cavity 7, and the concrete pouring pipe 30 may introduce concrete into the cavity 7 by an external pump 31. Such concrete pouring pipe 30 may be changed as necessary in various forms other than the form shown in the drawings.
도 5 는 본 발명의 용융된 원자로 연료봉을 처리하는 장치의 작동 방법을 도시한다. 도 5 의 (a)~(e)는 본 발명에 의하여 용융된 연료봉(6)이 내부 격납용기(1)로부터 분리되었을 때, 이를 원자로 하부의 주변 암반에 설치된 수직 공동(11)에 매립하는 과정을 도시한다. 5 illustrates a method of operation of an apparatus for treating molten reactor fuel rods of the present invention. 5 (a) to (e) is a process of embedding the molten fuel rod 6 in the vertical cavity 11 installed in the surrounding rock of the lower part of the reactor when the molten fuel rod 6 is separated from the internal containment vessel 1 according to the present invention To show.
도 5 의 (a)는 용융된 연료봉(6)이 내부 격납용기(1)로부터 분리되어 방수덮개(14)로 낙하하여 방수덮개(14)를 용융시키는 과정을 도시한다. 본 발명의 실시예에서는 내부 격납용기(1)의 오작동에 의하여 분리된 고온의 연료봉(6)이 방수덮개(14)와 접촉하여 용융시킨 후에, 두 버팀 블록(13)사이로 낙하하여 버팀 블록 덮개(12)위에 적층된다.FIG. 5A illustrates a process in which the molten fuel rod 6 is separated from the inner containment vessel 1 and falls into the waterproof cover 14 to melt the waterproof cover 14. In the embodiment of the present invention, after the hot fuel rod 6 separated by the malfunction of the inner containment container 1 is melted in contact with the waterproof cover 14, it is dropped between the two support blocks 13 and the support block cover ( 12) are stacked on.
이후, 도 5 의(b)에 도시된 바와 같이, 낙하한 연료봉(6)은 블록 버팀 덮개(12)를 용융시키고 용융대상물질(15)이 저장된 수직공동(11)으로 낙하하게 된다.Thereafter, as shown in FIG. 5B, the dropped fuel rod 6 melts the block prop cover 12 and falls into the vertical cavity 11 in which the melting target material 15 is stored.
이후, 도 5 의(c)에 도시된 바와 같이, 용융된 연료봉(6)이 수직공동(11)으로 낙하하여 적층되며 이후, 용융된 연료봉(6)의 반응열은 용융대상물질을 용융시키는 데 소모된다. 또한, 버팀 블록 덮개(12)가 파단되어 더 이상 서로 지지할 수 없는 두 차단블록(13)이 중앙을 향해 회전이동하게 된다.Thereafter, as shown in FIG. 5C, the molten fuel rods 6 fall into the vertical cavity 11 and are stacked, and then the heat of reaction of the molten fuel rods 6 is consumed to melt the material to be melted. do. In addition, the bracing block cover 12 is broken so that the two blocking blocks 13 that can no longer support each other are rotated toward the center.
이후, 도 5 의 (d)에 도시된 바와 같이, 회전한 두 차단블록(13)은 수직공동(11)을 밀폐시키고, 수직공동(11) 내부의 용융된 원료봉(6)은 용융대상물질과 수직공동(11) 주변의 암반을 용융시키며 서서히 냉각된다.Thereafter, as shown in (d) of FIG. 5, the two blocking blocks 13 rotated close the vertical cavity 11, and the molten raw material rod 6 inside the vertical cavity 11 is a melting target material. And the rock around the vertical cavity 11 is melted and gradually cooled.
이후, 도 5 의(e)에 도시된 바와 같이, 밀폐된 제1 격납용기에 연결된 콘크리트 타설용관으로 콘크리트를 유입시켜 콘크리트를 타설함으로써, 수직공동(11)을 외부와 완전히 격리시켜 주변으로 방사선이 유출되는 것을 방지할 수 있다.Subsequently, as shown in FIG. 5 (e), by pouring concrete into the concrete placing pipe connected to the sealed first containment container, the concrete is poured, thereby completely separating the vertical cavity 11 from the outside and radiating the radiation to the surroundings. Can be prevented from leaking.
이와 같은 구성에 의하여, 수직공동을 이용한 용융된 원자로 연료봉을 처리하는 장치는 사고 및 원자로의 비정상적인 가동 등에 의하여 원자로의 노심 냉각기능이 상실되고 원자로의 연료봉이 용융된 후 내부 격납용기가 파손되어, 용융된 핵 연료가 외부로 방출되는 중대사고가 발생되었을 경우, 동력이나 인력의 작동없이 자동적으로 내부에 설치된 골재나 콘크리트 등이 용융된 연료봉과 반응하도록 하여 에너지를 감소시키고, 원자력 발전소 하부의 지하 암반에 형성된 공동에 매립함으로써 장기간에 걸쳐 용융된 연료봉을 서서히 냉각시키는 효과를 발휘할 수 있다.With this configuration, the apparatus for processing the molten reactor fuel rod using the vertical cavity loses the core cooling function of the reactor due to an accident and abnormal operation of the reactor, and the internal containment vessel is broken after the fuel rod of the reactor melts, In the event of a serious accident in which the spent nuclear fuel is released to the outside, aggregates or concrete, etc. installed inside the reactor react with the molten fuel rods automatically without power or manpower to reduce the energy. By embedding in the formed cavity, it is possible to exert the effect of gradually cooling the molten fuel rod over a long period of time.
특히, 본 발명은 절리와 조인트를 그라우팅하고 지하 차수벽을 설치함으로써 지하수가 방사능에 오염되는 것을 방지할 수 있다.In particular, the present invention can prevent groundwater from being contaminated by radiation by grouting joints and joints and installing underground order walls.
특히, 본 발명은 내부 격납용기 주변에 연결된 콘크리트 타설용관으로 콘크리트를 주입시켜 내부에 콘크리트를 타설함으로써, 외부와 완전히 격리하여 주변으로 방사선이 방출되는 것을 방지할 수 있다.In particular, the present invention by injecting concrete into the concrete pouring pipe connected to the inner storage container surrounding the interior, it can be completely isolated from the outside to prevent radiation to be emitted to the surroundings.
이상 본 발명의 일실시예를 설명하였으나 본 발명의 기술적 사상이 상기 실시예에 한정되는 것은 아니며, 본 발명의 기술적 사상을 벗어나지 않는 범주에서 다양한 구성으로 구현할 수 있다.Although one embodiment of the present invention has been described above, the technical idea of the present invention is not limited to the above embodiment, and may be implemented in various configurations without departing from the technical idea of the present invention.

Claims (7)

  1. 원자로 하부의 절리 혹은 조인트를 그라우팅하여 지하수의 흐름을 차단하는 장치를 포함하는 용융된 원자로 연료봉을 처리하는 장치.A device for treating molten reactor fuel rods, comprising a device for cutting groundwater flow by grouting joints or joints under the reactor.
  2. 청구항 1에 있어서,The method according to claim 1,
    상기 원자로 하부에 위치하는 지하수 흐름을 차단하는, 상기 원자로를 둘러싸는 차수벽을 더 포함하는 것을 특징으로 하는 용융된 원자로 연료봉을 처리하는 장치.And an ordered wall surrounding said reactor to block groundwater flow located below said reactor.
  3. 청구항 1에 있어서,The method according to claim 1,
    원자로 하부에 위치하는 슬래브 및Slab located under the reactor and
    상기 슬래브로부터 하측으로 형성된 수직공동을 더 포함하는 용융된 원자로 연료봉을 처리하는 장치.And a vertical cavity formed downwardly from the slab.
  4. 청구항 3에 있어서,The method according to claim 3,
    상기 수직공동의 상부에 배치되는 한 개 이상의 차단블럭을 더 포함하는 것을 특징으로 하는 용융된 원자로 연료봉을 처리하는 장치.Apparatus for processing a molten reactor fuel rods further comprises at least one blocking block disposed above the vertical cavity.
  5. 청구항 4에 있어서,The method according to claim 4,
    상기 차단 블록을 정지시키는, 상기 수직공동을 덮는 버팀 덮개 또는 방수 덮개를 더 포함하는 것을 특징으로 하는 용융된 원자로 연료봉을 처리하는 장치.And a brace cover or a waterproof cover covering the vertical cavity to stop the blocking block.
  6. 청구항 5에 있어서,The method according to claim 5,
    상기 차단블럭은 상기 버팀 덮개 또는 방수 덮개가 제거되는 경우, 상기 수직공동을 밀폐시키도록 이동하는 것을 특징으로 하는 용융된 원자로 연료봉을 처리하는 장치.And the blocking block moves to seal the vertical cavity when the brace cover or the waterproof cover is removed.
  7. 청구항 3에 있어서,The method according to claim 3,
    외부로부터 콘크리트를 상기 수직공동 상부로 유입시킬 수 있는 콘크리트 타설용관을 더 포함하는 것을 특징으로 하는 용융된 원자로 연료봉을 처리하는 장치.Apparatus for processing the molten reactor fuel rods further comprises a concrete placing pipe for introducing concrete from the outside to the upper vertical cavity.
PCT/KR2012/006146 2011-08-12 2012-08-01 Apparatus for treating molten atomic reactor fuel rod using vertical cavity WO2013024994A2 (en)

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CN201280039502.4A CN103733266B (en) 2011-08-12 2012-08-01 For using the equipment of the nuclear reactor fuel rod of vertical chamber process melting

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KR20110080742 2011-08-12
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KR1020110096313A KR101278196B1 (en) 2011-08-12 2011-09-23 Apparatus with vertical hole for treating a melted fuel rod of nuclear reactor

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Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH06109885A (en) * 1991-11-06 1994-04-22 Commiss Energ Atom Nuclear reactor having device for recovering reactor core after accidental melt-down of nuclear reactor
JP2003530274A (en) * 2000-04-07 2003-10-14 ニューコン コーポレイション Drop box container
JP2005241527A (en) * 2004-02-27 2005-09-08 Ishikawajima Harima Heavy Ind Co Ltd Method of dismantling nuclear reactor facility
KR20070111102A (en) * 2006-05-17 2007-11-21 에코랜드 주식회사 Reactive grouting method and cutoff reinforcement
KR100970497B1 (en) * 2009-12-31 2010-07-16 주식회사 한국 지오텍 Method for managing knowledge-based injection construction using automatic grouting system

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH06109885A (en) * 1991-11-06 1994-04-22 Commiss Energ Atom Nuclear reactor having device for recovering reactor core after accidental melt-down of nuclear reactor
JP2003530274A (en) * 2000-04-07 2003-10-14 ニューコン コーポレイション Drop box container
JP2005241527A (en) * 2004-02-27 2005-09-08 Ishikawajima Harima Heavy Ind Co Ltd Method of dismantling nuclear reactor facility
KR20070111102A (en) * 2006-05-17 2007-11-21 에코랜드 주식회사 Reactive grouting method and cutoff reinforcement
KR100970497B1 (en) * 2009-12-31 2010-07-16 주식회사 한국 지오텍 Method for managing knowledge-based injection construction using automatic grouting system

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