KR101029444B1 - External reactor vessel cooling system using a dedicated water storage tank and a seal plate - Google Patents

External reactor vessel cooling system using a dedicated water storage tank and a seal plate Download PDF

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KR101029444B1
KR101029444B1 KR1020100062425A KR20100062425A KR101029444B1 KR 101029444 B1 KR101029444 B1 KR 101029444B1 KR 1020100062425 A KR1020100062425 A KR 1020100062425A KR 20100062425 A KR20100062425 A KR 20100062425A KR 101029444 B1 KR101029444 B1 KR 101029444B1
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South Korea
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reactor
reactor vessel
sealing plate
cooling water
dedicated water
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KR1020100062425A
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Korean (ko)
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이상섭
이의종
김성환
김병섭
이광원
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한국수력원자력 주식회사
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/028—Seals, e.g. for pressure vessels or containment vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • 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

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

Abstract

PURPOSE: A system for cooling the external wall of a reactor vessel using a dedicated water tub and a sealing plate is provided to safely cool a core melt by supplying coolants to a filling space with gravity. CONSTITUTION: A dedicated water tub(4) is installed on a reactor building(1). The dedicated water tub stores coolants. A sealing plate(7) is installed in the inner wall of a reactor structure(9). The sealing plate shortens the filling time of the coolants in a reactor cavity. A coolant supply unit includes a coolant supply tube(5) and a supply valve(6). The coolant supply tube supplies coolants to the filling space.

Description

전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템{External Reactor Vessel Cooling System Using A Dedicated Water Storage Tank and A Seal Plate}External Reactor Vessel Cooling System Using A Dedicated Water Storage Tank and A Seal Plate}

본 발명은 원자력발전소의 노심용융사고시 원자로용기 외벽을 신속하고 안정적으로 냉각시킬 수 있는 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템에 관한 것이다.The present invention relates to a reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate that can quickly and stably cool the reactor vessel outer wall during the core meltdown accident of a nuclear power plant.

원자력발전소에서 중대사고 발생시 노심용융물이 원자로용기의 파손부를 통해 원자로 공동으로 낙하할 가능성이 있다. 여기서 노심용융물이란 원자로용기의 내부에 설치되는 원자로 노심의 핵연료인 농축우라늄과, 피복재로 사용되는 지르코늄과, 제어봉 물질인 은과 카드뮴 및 상기 원자로용기를 구성하는 다수의 물질들이 혼합된 고온의 용융물질을 말한다.In the event of a serious accident at a nuclear power plant, the core melt may fall into the reactor cavity through the breakage of the reactor vessel. Here, the core melt refers to a high temperature molten material in which enriched uranium, a nuclear fuel of a reactor core installed inside a reactor vessel, zirconium used as a cladding material, silver and cadmium, which are control rod materials, and a plurality of materials constituting the reactor vessel are mixed. Say

상기 노심용융물은 그 내부의 핵분열 생성물의 붕괴로 열을 발생시키게 되므로, 추가적인 피해를 줄이기 위해서는 노심용융물을 신속히 냉각시킬 필요가 있다.Since the core melt generates heat due to the collapse of the nuclear fission product therein, it is necessary to cool the core melt quickly to reduce further damage.

종래에는 노심용융사고시 노심용융물을 냉각시키기 위해 펌프를 작동시켜 원자로건물 내 재장전수조(In-Containment Refueling Water Storage Tank ; IRWST)의 냉각수를 원자로 공동에 공급하여 노심용융물을 냉각시키고, 원자로 공동에 냉각수를 충진한 후에 증발되는 냉각수는 붕산수보충펌프(BAMP)를 작동시켜 보충하는 방식을 사용하였다.Conventionally, the pump is operated to cool the core melt in the core meltdown supply, thereby supplying the cooling water of the In-Containment Refueling Water Storage Tank (IRWST) to the reactor cavity to cool the core melt, and the cooling water to the reactor cavity. Cooling water evaporated after the filling was used to supplement the boric acid supplement pump (BAMP) by operating.

그러나 이와 같은 종래의 냉각 시스템은 능동형 펌프를 사용하여 냉각수를 공급하게 되므로 펌프에 전원이 공급되지 않는 등의 사고 발생시에는 적절한 대응이 어려운 문제점이 있었다.However, such a conventional cooling system has a problem that it is difficult to properly respond to an accident, such as the power is not supplied to the pump because the cooling water is supplied using the active pump.

또한 원자로 공동은 그 부피가 크기 때문에 종래의 냉각 시스템에 의할 경우 냉각수의 충진 완료시까지 시간이 과도하게 소요되어 노심용융물을 신속하게 냉각시키기 어려운 문제점이 있었다.In addition, since the reactor cavity has a large volume, the conventional cooling system has a problem that it takes too long to complete the filling of the cooling water, which makes it difficult to quickly cool the core melt.

본 발명은 상기와 같은 문제점을 해결하기 위하여 안출된 것으로서, 원자력발전소에서 중대사고시 발생되는 노심용융물을 안전하고 신속하게 냉각시킬 수 있는 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템을 제공함에 그 목적이 있다.The present invention has been made to solve the above problems, to provide a reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate that can safely and quickly cool the core melt generated during a serious accident in a nuclear power plant. There is this.

상술한 바와 같은 목적을 구현하기 위한 본 발명의 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템은, 원자로건물의 상부에 설치되고 노심용융사고시 원자로용기를 냉각하기 위한 냉각수가 저장되는 전용수조; 상기 원자로용기가 설치되는 원자로 공동 내에 냉각수의 충진시간을 단축시키기 위해 상기 원자로용기의 하측에 인접하여 원자로 공동 구조물의 내벽에 그 둘레가 밀착 설치되는 밀봉판; 및 상기 전용수조에 저장된 냉각수를 상기 밀봉판과 상기 원자로 공동 구조물의 내벽으로 둘러싸인 충진공간으로 공급하는 냉각수공급관과, 상기 냉각수공급관의 유로상에 설치되는 공급밸브를 포함하는 냉각수공급부를 포함한다.Reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate of the present invention for achieving the above object, the dedicated tank is installed on the top of the reactor building and the cooling water for cooling the reactor vessel during the core meltdown accident; A sealing plate installed close to the inner wall of the reactor cavity structure adjacent to the lower side of the reactor vessel to shorten the filling time of the cooling water in the reactor cavity in which the reactor vessel is installed; And a cooling water supply pipe for supplying the cooling water stored in the dedicated water tank to the filling space surrounded by the sealing plate and the inner wall of the reactor cavity structure, and a supply valve installed on the flow path of the cooling water supply pipe.

상기 밀봉판에는 상기 원자로용기 하부에 연결된 노내계측기(ICI) 가이드 튜브가 기밀이 유지된 상태로 관통하는 통과공이 형성되어 있는 것을 특징으로 한다.The sealing plate is characterized in that the through-hole is formed through the furnace measuring instrument (ICI) guide tube connected to the lower portion of the reactor vessel is maintained in the airtight state.

본 발명에 따른 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템에 의하면, 원자력발전소에서 설계기준을 초과하여 노심이 용융되는 중대사고시 원자로용기 냉각용 전용수조를 원자로건물 상부에 설치하고, 능동형 펌프 대신 중력에 의한 자연구동력으로 냉각수를 원자로용기 외벽을 둘러싸는 충진공간에 공급함으로써, 교류전원이 공급되지 않는 사고발생시에도 냉각수를 안정적으로 공급하여 원자로용기의 건전성을 보장할 수 있다.According to the reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate according to the present invention, in the case of a serious accident in which the core melts in excess of the design criteria in a nuclear power plant, a dedicated water tank for cooling the reactor vessel is installed above the reactor building, and instead of an active pump. By supplying the coolant to the filling space surrounding the outer wall of the reactor vessel by natural driving force by gravity, it is possible to guarantee the soundness of the reactor vessel by stably supplying the coolant even in the event of an accident in which AC power is not supplied.

또한 본 발명에 의하면, 원자로용기 공동에 밀봉판을 설치하여 냉각수의 충진공간을 감소시킴으로써 원자로 공동 내 냉각수의 충진시간이 단축되어 원자로용기를 신속하게 냉각시킬 수 있다.In addition, according to the present invention, by installing a sealing plate in the reactor vessel cavity to reduce the filling space of the cooling water, the filling time of the cooling water in the reactor cavity can be shortened to quickly cool the reactor vessel.

도 1은 본 발명에 따른 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템의 단면도,
도 2는 도 1에 도시된 밀봉판의 사시도,
도 3은 본 발명에 따른 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템에서 냉각수가 충진된 상태를 보여주는 단면도이다.1 is a cross-sectional view of the reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate according to the present invention,
2 is a perspective view of the sealing plate shown in FIG.
3 is a cross-sectional view showing a state in which coolant is filled in a reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate according to the present invention.

이하 첨부한 도면을 참조하여 본 발명의 바람직한 실시예에 대한 구성 및 작용을 상세히 설명하면 다음과 같다. Hereinafter, the configuration and operation of the preferred embodiment of the present invention will be described in detail with reference to the accompanying drawings.

도 1은 본 발명에 따른 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템의 단면도, 도 2는 도 1에 도시된 밀봉판의 사시도이다.1 is a cross-sectional view of the reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate according to the present invention, Figure 2 is a perspective view of the sealing plate shown in FIG.

본 발명에 따른 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템은, 원자로건물(1)의 상부에 설치되고 노심용융사고시 원자로용기(2)를 냉각하기 위한 냉각수가 저장되는 전용수조(4)와, 상기 원자로용기(2)가 설치되는 원자로건물(1) 하부의 원자로 공동 내에 냉각수의 충진시간을 단축시키기 위해 상기 원자로용기(2)의 하측에 인접하여 원자로 공동 구조물(9)의 내벽에 밀착 설치되는 밀봉판(7) 및 상기 전용수조(4)에 저장된 냉각수를 상기 밀봉판(7) 상측과 상기 원자로 공동 구조물(9)의 내벽으로 둘러싸인 충진공간으로 공급하는 냉각수공급부를 포함한다.Reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate according to the present invention, and installed in the upper portion of the reactor building (1) and the dedicated water tank (4) is stored in the cooling water for cooling the reactor vessel (2) in the core meltdown and Adjacent to the inner wall of the reactor cavity structure 9 adjacent to the lower side of the reactor vessel 2 in order to shorten the filling time of the coolant in the reactor cavity under the reactor building 1 in which the reactor vessel 2 is installed. And a cooling water supply unit for supplying the cooling water stored in the sealing plate 7 and the dedicated water tank 4 to the filling space surrounded by the upper side of the sealing plate 7 and the inner wall of the reactor cavity structure 9.

원자로건물(1)은 통상 콘크리트 구조물로 이루어지고, 원자로건물(1)의 상부에는 전용수조(4)가 위치하며, 원자로건물(1)의 원자로 공동 구조물(9)의 내부 공간인 원자로 공동에는 원자로용기(2)가 설치된다. 또한 상기 원자로용기(2)의 양측에는 원자로용기(2)에서 가열된 냉각수를 이용하여 증기를 발생시켜 원자로건물(1) 외부의 터빈에 공급하는 증기발생기(3)가 설치된다. Reactor building (1) is usually made of a concrete structure, a dedicated water tank (4) is located on top of the reactor building (1), the reactor cavity in the reactor cavity, which is the inner space of the reactor cavity structure (9) of the reactor building (1) The container 2 is installed. In addition, both sides of the reactor vessel (2) is provided with a steam generator (3) for generating steam using the cooling water heated in the reactor vessel (2) to supply to the turbine outside the reactor building (1).

상기 원자로용기(2)의 외측면과 원자로 공동 구조물(9)의 내벽과 밀봉판(7)의 상면으로 둘러싸인 내부 공간은 노심용융사고시 원자로용기(2)를 냉각하기 위해 공급되는 냉각수의 충진공간이 된다.The inner space surrounded by the outer surface of the reactor vessel (2), the inner wall of the reactor cavity structure (9), and the upper surface of the sealing plate (7) has a filling space of cooling water supplied to cool the reactor vessel (2) during the core meltdown accident. do.

상기 전용수조(4)에 저장된 냉각수를 상기 원자로 공동으로 공급하는 냉각수공급부는, 상기 전용수조(4)와 원자로 공동 사이를 연결하는 냉각수공급관(5)과, 상기 냉각수공급관(5)의 냉각수 유로상에 설치되어 냉각수의 공급을 단속하는 공급밸브(6)를 포함한다.The cooling water supply unit for supplying the cooling water stored in the dedicated water tank 4 to the reactor cavity includes a cooling water supply pipe 5 connecting the dedicated water tank 4 and the reactor cavity, and a cooling water flow path of the cooling water supply pipe 5. It is provided in the supply valve 6 for regulating the supply of cooling water.

상기 전용수조(4)에 수용되어 있는 냉각수는 공급밸브(6)의 개방시 중력에 의해 냉각수공급관(5)을 따라 하측으로 이동되어 원자로 공동의 충진공간으로 공급되도록 원자로 공동의 상측에 설치된다. 상기 공급밸브(6)는 중대사고시 운전원의 조치에 의해 개방되며, 구동전원은 교류(AC)전원이 사용될 수 있으나, 교류(AC)전원의 상실시에도 공급밸브(6)가 작동될 수 있도록 교류(AC)전원 이외에 직류(DC)전원이 선택적으로 사용되는 것으로 구성됨이 바람직하다.Cooling water contained in the dedicated water tank (4) is installed on the upper side of the reactor cavity to be moved downward along the cooling water supply pipe (5) by gravity when opening the supply valve (6) to supply to the filling space of the reactor cavity. The supply valve (6) is opened by the operator's action in the event of a serious accident, the drive power may be alternating current (AC) power may be used, the alternating current so that the supply valve (6) can be operated even when the AC power (AC) power In addition to the (AC) power source, a direct current (DC) power source is preferably configured to be used selectively.

상기 원자로 공동 구조물(9)의 내부 공간인 원자로 공동에는 원자로용기(2) 하부의 가장자리부가 안착되는 단턱이 형성되어 있고, 원자로용기(2)의 하부에는 그 내부 노심의 중성자속 및 온도 등을 측정하는 노내계측기(In-core Instrument ; ICI)의 가이드 튜브(8)가 전기적으로 연결되어 원자로 공동의 하부 공간으로 돌출되어 있다.In the reactor cavity, which is an inner space of the reactor cavity structure 9, a stepped portion is formed in which the edge portion of the lower portion of the reactor vessel 2 is seated, and at the lower portion of the reactor vessel 2, neutron flux and temperature of the inner core are measured. The guide tube 8 of the In-core Instrument (ICI) is electrically connected to protrude into the lower space of the reactor cavity.

상기 밀봉판(7)은 원자로용기(2) 하측에 위치하며, 스테인레스 스틸로 제작된다. 상기 밀봉판(7)은 원자로용기(2) 하측에 인접하게 횡방향으로 설치되며, 그 둘레는 원자로 공동 구조물(9)의 내벽에 밀착된다. 그리고 상기 밀봉판(7)에는 상기 노내계측기 가이드 튜브(8)가 관통하는 다수의 통과공(10)이 형성되어 있고, 냉각수가 밀봉판(7)의 하부로 누설되지 않도록 상기 통과공(10)과 노내계측기 가이드 튜브(8) 사이는 밀봉처리되어 있다.The sealing plate 7 is located under the reactor vessel 2 and is made of stainless steel. The sealing plate 7 is installed in the transverse direction adjacent to the lower side of the reactor vessel 2, the perimeter of which is in close contact with the inner wall of the reactor cavity structure 9. The sealing plate 7 has a plurality of through holes 10 through which the furnace measuring instrument guide tube 8 penetrates, and the cooling holes 10 do not leak to the lower part of the sealing plate 7. And the furnace measuring instrument guide tube 8 are sealed.

상기 밀봉판(7)이 설치됨에 따라서 전용수조(4)로부터 공급되는 냉각수는 원자로용기(2)에 인접한 밀봉판(7)의 상부 공간에만 충진되고, 원자로용기(2)와 떨어져 있는 밀봉판(7)의 하부 공간에는 충진되지 않으며, 이에 따라 냉각수의 충진공간 및 충진시간을 단축할 수 있게 된다.As the sealing plate 7 is installed, the cooling water supplied from the dedicated water tank 4 is filled only in the upper space of the sealing plate 7 adjacent to the reactor vessel 2, and the sealing plate separated from the reactor vessel 2 ( The lower space of 7) is not filled, thereby shortening the filling space and filling time of the cooling water.

도 3은 본 발명에 따른 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템에서 냉각수가 충진된 상태를 보여주는 단면도이다.3 is a cross-sectional view showing a state in which coolant is filled in a reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate according to the present invention.

이하 도 3을 참조하여 노심용융사고 발생시 원자로용기(2)의 냉각 작용을 설명한다.Hereinafter, the cooling operation of the reactor vessel 2 in the case of a core meltdown accident will be described with reference to FIG. 3.

노심용융사고가 발생하면, 운전원은 공급밸브(6)를 개방시킨다. 상기 공급밸브(6)는 DC 전원 등 교류전원의 상실시에도 작동될 수 있는 구동원에 의해 작동되므로 교류전원의 공급이 불안정한 상황에서도 안정적으로 작동할 수 있다.When a core meltdown accident occurs, the operator opens the supply valve 6. The supply valve 6 is operated by a drive source that can be operated even when the AC power source, such as DC power, can be operated stably even in a situation where the supply of AC power is unstable.

공급밸브(6)가 개방되면, 전용수조(4)에 저장된 냉각수가 냉각수공급관(5) 및 공급밸브(6)를 거쳐 원자로 공동의 충진공간으로 공급된다. 이 때 밀봉판(7)의 하부 공간에는 냉각수가 충진되지 않기 때문에 냉각수의 충진은 신속히 이루어지게 된다. 신속히 충진된 냉각수는 노심용융물을 냉각하여 추가적인 피해를 방지하게 된다.When the supply valve 6 is opened, the cooling water stored in the dedicated water tank 4 is supplied to the filling space of the reactor cavity via the cooling water supply pipe 5 and the supply valve 6. At this time, since the cooling water is not filled in the lower space of the sealing plate 7, the cooling water is filled quickly. Rapidly charged coolant cools the core melt to prevent further damage.

이상의 설명에서 전용수조(4)의 냉각수는 능동형 펌프와 같은 별도의 구동수단 없이 중력에 의해서만 충진공간으로 공급된다. 따라서 전원공급에 이상이 있는 상황에서도 노심용융물을 확실하게 냉각시킬 수 있다.
In the above description, the cooling water of the dedicated water tank 4 is supplied to the filling space only by gravity without a separate driving means such as an active pump. Therefore, the core melt can be reliably cooled even in the event of an abnormal power supply.

1 : 원자로건물
2 : 원자로용기
3 : 증기발생기
4 : 전용수조
5 : 냉각수공급관
6 : 공급밸브
7 : 밀봉판
8 : 노내계측기(ICI) 가이드 튜브
9 : 원자로 공동 구조물
10 : 통과공1: Reactor Building
2: reactor vessel
3: steam generator
4: dedicated water tank
5: cooling water supply pipe
6: supply valve
7: sealing plate
8: ICI guide tube
9: reactor cavity structure
10: through hole

Claims (2)

원자로건물의 상부에 설치되고 노심용융사고시 원자로용기를 냉각하기 위한 냉각수가 저장되는 전용수조;
상기 원자로용기가 설치되며 상기 원자로건물 하부에 구비되는 원자로 공동 내에 냉각수의 충진시간을 단축시키기 위해 상기 원자로용기의 하측에 인접하여 원자로 공동 구조물의 내벽에 그 둘레가 밀착 설치되는 밀봉판; 및
상기 전용수조에 저장된 냉각수를 상기 원자로용기의 외측면과 상기 밀봉판의 상면 및 상기 원자로 공동 구조물의 내벽으로 둘러싸인 충진공간으로 공급하는 냉각수공급관과, 상기 냉각수공급관의 유로상에 설치되며 교류(AC)전원 이외에 직류(DC)전원으로도 작동되는 공급밸브를 포함하는 냉각수공급부;
를 포함하는 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템.
A dedicated water tank installed on top of the reactor building and storing coolant for cooling the reactor vessel during the core meltdown accident;
A sealing plate in which the reactor vessel is installed and a circumference of the reactor vessel is installed in close proximity to the inner wall of the reactor cavity structure adjacent to the lower side of the reactor vessel to shorten the filling time of the cooling water in the reactor cavity provided under the reactor building; And
A cooling water supply pipe for supplying cooling water stored in the dedicated water tank to a filling space surrounded by an outer surface of the reactor vessel, an upper surface of the sealing plate, and an inner wall of the reactor cavity structure, and an alternating current (AC) Cooling water supply unit including a supply valve which is operated in addition to the power supply (DC) power source;
Reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate comprising a.
제1항에 있어서,
상기 밀봉판에는 상기 원자로용기 하부에 연결된 노내계측기(ICI) 가이드 튜브가 기밀이 유지된 상태로 관통하는 통과공이 형성되어 있는 것을 특징으로 하는 전용수조 및 밀봉판을 이용한 원자로용기 외벽 냉각 시스템.

The method of claim 1,
Reactor vessel outer wall cooling system using a dedicated water tank and a sealing plate is formed in the sealing plate through the through-hole hole through which the furnace internal instrument (ICI) guide tube connected to the lower portion of the reactor vessel is kept airtight.

KR1020100062425A 2010-06-30 2010-06-30 External reactor vessel cooling system using a dedicated water storage tank and a seal plate KR101029444B1 (en)

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KR100804405B1 (en) 2007-02-28 2008-02-15 한국원자력연구원 Coolant circulation apparatus through gap between reactor and insulation under external reactor vessel cooling and method thereof
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KR960011210B1 (en) * 1992-10-19 1996-08-21 한국과학기술원 A pressurized water reactor of a passive type
KR20060117651A (en) * 2005-05-13 2006-11-17 재단법인서울대학교산학협력재단 System for cooling the exterior wall of a reactor vessel and the method thereof
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