KR20140122979A - Cooling system for nuclear power plant by using water - Google Patents

Cooling system for nuclear power plant by using water Download PDF

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KR20140122979A
KR20140122979A KR20130040137A KR20130040137A KR20140122979A KR 20140122979 A KR20140122979 A KR 20140122979A KR 20130040137 A KR20130040137 A KR 20130040137A KR 20130040137 A KR20130040137 A KR 20130040137A KR 20140122979 A KR20140122979 A KR 20140122979A
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South Korea
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emergency
cooling system
reactor
tank
water
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KR20130040137A
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Korean (ko)
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이필승
이정익
이기환
이강헌
정용훈
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한국과학기술원
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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
    • 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
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • G21C15/06—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
    • 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
    • G21C15/24—Promoting flow of the coolant
    • G21C15/257—Promoting flow of the coolant using heat-pipes
    • 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

Abstract

The present invention relates to an emergency cooling system for a nuclear power plant, using seawater. The emergency cooling system comprises an active emergency cooling system composed of an emergency core cooling system (ECCS), a containment spray system (CSS), and an in-vessel retention (IVR). The emergency cooling system includes a ballasting tank connected to seawater; an emergency passive containment cooling system (EPCCS) reducing temperature and pressure inside a nuclear reactor by using the seawater supplied to the ballasting tank as emergency cooling water; and an emergency passive reactor vessel cooling system (EPRVCS) reducing temperature and pressure inside a reactor by using the seawater supplied to the ballasting tank as emergency cooling water. According to the present invention, the system immediately supplies the seawater without supplying external power to maintain a cooling state of the nuclear power plant by a natural differential head, thereby maintaining safety of the nuclear power plant.

Description

해수를 이용한 원전 비상냉각 시스템{COOLING SYSTEM FOR NUCLEAR POWER PLANT BY USING WATER}TECHNICAL FIELD [0001] The present invention relates to an emergency cooling system using seawater,

본 발명은 해수를 이용한 원전 비상냉각 시스템에 관한 것으로서, 보다 상세하게는 평상시의 비상냉각 시스템과 더불어, 해상 원전에서 해수를 유입시킴으로 원자로 등의 냉각 상태를 유지시키는 해양원전 비상냉각 시스템에 관한 것이다.The present invention relates to a nuclear emergency cooling system using seawater, and more particularly, to an emergency cooling system for a marine nuclear reactor that keeps the cooling state of a reactor or the like by introducing seawater into a nuclear power plant in addition to a normal emergency cooling system.

일반적으로 원자력 발전소는 유용한 전력자원으로 사용되어져 왔으나, 과거 체르노빌이나 최근 일본의 후쿠시마 원전 사태에서 나타났듯이, 발전소에 예상치 못한 이상이 발생했을 때, 주변의 광범위한 지역에 환경적으로 치명적인 해악을 끼칠 수 있다는 점에서 유용성 못지않은 위험한 시설로 인식되는 문제점이 있었다.In general, nuclear power plants have been used as useful power resources. However, as the Chernobyl and recent Fukushima nuclear power plants in Japan have shown, unexpected failures in power plants can cause environmental damages to a wide area around them. There is a problem that it is recognized as a dangerous facility which is equal to usability.

특히 원자로에 냉각수가 공급되지 않음에 의해 노심이 노출되어 녹아서 발생하는 상황은 주변 지역으로의 방사능 유출을 발생시켜 매우 치명적인 위험을 초래하게 되는 것임에도, 현재까지 그러한 비상상황 발생 시 관리자의 상황 파악 후의 인위적인 제어가 이루어지도록 기다리게 하지 않고, 또한 외부 동력의 공급 없이도 신속하게 이루어질 해결 조치에 대한 연구는 미비한 상태에 있는 문제점이 있다.Especially, when the core is exposed and melted due to no cooling water being supplied to the reactor, it causes radiation leakage to the surrounding area, resulting in a very lethal danger. However, in the case of such an emergency, There is a problem in that there is insufficient research on the solution measures to be made promptly without waiting for the artificial control to be performed and without supplying external power.

도 1은 일반적인 육상원전 비상냉각 시스템의 개략적 구조를 나타내는 모식도이다. 1 is a schematic diagram showing a schematic structure of a general onshore nuclear reactor emergency cooling system.

일반적인 육상원전 비상냉각 시스템은 ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)로 이루어져 있으며, 원자력 발전소에 소외전원공급이 차단되고 비상디젤 발전기가 작동되지 않으면 육상원전 비상 냉각 시스템은 모두 작동되지 못한다.A typical onshore nuclear emergency cooling system consists of ECCS (Emergency Core Cooling System), CSS (Containment Spray System) and IVR (In-Vessel Retention). If the emergency power supply to the nuclear power plant is cut off and the emergency diesel generator is not operated, Nuclear emergency cooling systems can not be operated at all.

KRKR 10-2011-009156510-2011-0091565 AA

따라서, 본 발명의 목적은 이와 같은 문제점을 해결하기 위해 창안된 것으로서, 원전의 전력 시스템 등의 이상 발생에 의하여 평상시의 냉각 시스템이 작동 불능 상태가 될 경우, 외부 동력의 공급 없이도 자연 수두차를 이용하여 즉각적으로 해수를 유입시키도록 하는 시스템을 작동함으로써, 충분히 공급되는 해수를 이용하여 원자로 등의 냉각 상태를 유지시켜 원전의 안전을 유지하도록 하는데 있다.SUMMARY OF THE INVENTION Accordingly, it is an object of the present invention to provide an electric power steering system and an electric power steering system in which when a normal cooling system becomes inoperable due to an abnormality of a power system of a nuclear power plant, And the system is operated so that seawater can be immediately introduced into the reactor, thereby maintaining the cooling state of the nuclear reactor using the fully supplied seawater so as to maintain the safety of the nuclear reactor.

또한, 평상시의 냉각 시스템이 작동 상태일 경우에도, 부가적으로 외부 동력의 공급 없이도 자연 수두차를 이용하여 해수를 유입시키는 시스템을 작동함으로써, 원전의 안전을 유지하는데 있다.In addition, even when the normal cooling system is in an operating state, the system is operated to inflow seawater by using the natural head difference without additionally supplying external power to maintain the safety of the nuclear power plant.

이와 같은 목적을 달성하기 위하여 본 발명에 따른 해상에 설치된 원전의 비상냉각 시스템은, ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)로 이루어진 원전의 능동(Active) 비상냉각 시스템을 포함하여, 해수와 연결된 발라스팅 탱크와; 상기 발라스팅 탱크에 유입된 해수를 비상 냉각수로 이용하여 원자로 내부의 온도와 압력을 낮추는 EPCCS(Emergence Passive Containment Cooling System)와; 상기 발라스팅 탱크에 유입된 해수를 비상 냉각수로 이용하여 반응로(reactor) 내부의 온도와 압력을 낮추는 EPRVCS(Emergence Passive Reactor Vessel Cooling System)를 포함한다.In order to achieve the above object, according to the present invention, there is provided an emergency cooling system for a nuclear power plant installed on the sea, comprising: an active (active) nuclear power plant comprising an Emergency Core Cooling System (ECCS), a Containment Spray System (CSS), and an IVR A ballasting tank connected to the seawater, including an emergency cooling system; An EPCCS (Emergency Passive Containment Cooling System) for reducing the temperature and pressure inside the nuclear reactor using seawater introduced into the ballasting tank as emergency cooling water; And an EPRVCS (Emergence Passive Reactor Vessel Cooling System) that uses the seawater introduced into the ballasting tank as emergency cooling water to lower the temperature and pressure inside the reactor.

그리고, 상기 EPCCS(Emergency Passive Containment Cooling System)는, 원자로 내부에 설치되는 열 교환기(heat exchanger)와; 상기 열 교환기에 상기 발라스팅 탱크의 비상 냉각수를 공급하는 발라스트 워터 파이프 라인과; 상기 열 교환기부터 발생되는 스팀을 상기 발라스팅 탱크에 전달하는 스팀 전달 파이프 라인을 포함한다.The EPCCS (Emergency Passive Containment Cooling System) includes: a heat exchanger installed inside a reactor; A ballast water pipeline for supplying emergency cooling water of the ballasting tank to the heat exchanger; And a steam delivery pipeline for delivering steam generated from the heat exchanger to the ballasting tank.

또한, 상기 EPCCS(Emergency Passive Containment Cooling system)는 원자로 내부와 상기 발라스팅 탱크 사이에 원자로 내부의 압력 및 온도를 상쇄시키는 필터링부를 포함한다.The EPCCS (Emergency Passive Containment Cooling system) includes a filtering unit for canceling the pressure and the temperature inside the reactor between the inside of the reactor and the ballasting tank.

상기 열 교환기 및 발라스트 워터 파이프 라인과 스팀 전달 파이프 라인, 필터링부는 상기 냉각수의 자유수면의 높이보다 낮은 것을 특징으로 한다.And the heat exchanger, the ballast water pipeline, the steam delivery pipeline, and the filtering section are lower than the height of the free water surface of the cooling water.

또한 상기 발라스팅 탱크는, 상기 발라스팅 탱크 내부의 스팀 배출과 내부의 온도 및 기압을 낮추는 피동 밸브를 포함한다.The ballasting tank also includes a discharge valve for discharging steam inside the ballasting tank and lowering the internal temperature and the air pressure.

상기 EPRVCS(Emergency Passive Reactor Vessel Cooling System)는 반응로(reactor)에 연결되어 상기 발라스팅 탱크의 비상 냉각수가 유입되는 반응조 리텐션 파이프 라인을 포함할 수 있다.The EPRVCS (Emergency Passive Reactor Vessel Cooling System) may include a reaction tank retention pipeline connected to a reactor to supply emergency cooling water of the ballasting tank.

그리고, 상기 반응로에서 생성되는 스팀은 상기 EPCCS를 통해 응축되어 IRWST(In-containment Refueling Water Storage Tank)에 저장되며, 상기 반응로 및 반응조 리텐션 파이프 라인은 냉각수의 자유수면 높이 보다 낮은 것을 특징으로 한다.The steam generated in the reactor is condensed through the EPCCS and stored in an IRWST (In-containment Refueling Water Storage Tank), and the reactor and the reactor retention pipeline are lower than the free water surface height of the cooling water. do.

본 발명의 또 다른 측면에 따르면, 해상에 설치된 원전의 비상냉각 방법은 상기 ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)로 이루어진 원전의 능동(Active) 비상냉각 시스템의 작동 유무와 관계없이, 발라스팅 탱크에 유입된 비상 냉각수를 원자로 내부의 열 교환기(heat exchanger)에 공급하는 단계와; 상기 공급된 비상 냉각수를 통하여 냉각된 열 교환기의 스팀을 발라스팅 탱크에 배출하는 단계를 포함한다.According to another aspect of the present invention, an emergency cooling method of a nuclear power plant installed on the sea is an active emergency of nuclear power plants composed of ECCS (Emergency Core Cooling System), CSS (Containment Spray System) and IVR (In-Vessel Retention) Supplying the emergency cooling water introduced into the ballasting tank to a heat exchanger inside the reactor, regardless of whether the cooling system is operated or not; And discharging the steam of the heat exchanger cooled through the supplied emergency cooling water to the ballasting tank.

본 발명의 또 다른 측면에 따르면, 해상에 설치된 원전의 비상냉각 방법은 ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)로 이루어진 원전의 능동(Active) 비상냉각 시스템의 작동 유무와 관계없이, 상기 발라스팅 탱크에 유입된 비상 냉각수가 반응로에 유입되는 단계와; 상기 유입된 비상 냉각수에 의해 반응로가 냉각되는 단계를 포함한다.According to another aspect of the present invention, an emergency cooling method of a nuclear power plant installed on the ocean is an active emergency cooling of a nuclear power plant composed of ECCS (Emergency Core Cooling System), CSS (Containment Spray System) and IVR Regardless of whether the system is operated or not, the emergency cooling water flowing into the ballasting tank flows into the reaction furnace; And cooling the reactor by the introduced emergency cooling water.

상기한 바와 같이, 본 발명에 따른 해양원전 비상냉각 시스템은 원전의 전력 시스템 등의 이상 발생에 의하여 평상시의 냉각 시스템이 작동 상태이거나 불능 상태와 관계없이, 외부 동력의 공급없이도 자연 수두차를 이용하여 즉각적으로 해수를 유입시키도록 하는 시스템을 작동함으로써, 충분히 공급되는 해수를 이용하여 원자로 등의 냉각 상태를 유지시켜 원전의 안전을 유지하도록 하는 효과가 있다.As described above, in the marine nuclear emergency cooling system according to the present invention, the abnormality of the power system of the nuclear power plant causes the normal cooling system to operate using the natural water head without any external power supply, It is possible to maintain the safety of the nuclear power plant by maintaining the cooling state of the reactor or the like by using the seawater sufficiently supplied by operating the system for promptly introducing the seawater.

도 1은 일반적인 육상원전 비상냉각 시스템의 개략적 구조를 도시한 도면.
도 2는 본 발명에 따른 해양원전 비상냉각 시스템의 개략적 구조를 도시한 도면.
도 3은 본 발명에 따른 해양원전 비상냉각 시스템을 다수개로 구성한 도면.BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 shows a schematic structure of a typical onshore nuclear emergency cooling system; FIG.
2 shows a schematic structure of a marine nuclear reactor emergency cooling system according to the present invention.
3 is a view showing a plurality of marine nuclear emergency cooling systems according to the present invention.

이하 첨부된 도면을 참조로 본 발명의 바람직한 실시예를 상세히 설명하기로 한다. 이에 앞서, 본 명세서 및 청구범위에 사용된 용어나 단어는 통상적이거나 사전적인 의미로 한정해서는 아니되며, 발명자는 그 자신의 발명을 가장 최선의 방법으로 설명하기 위해 용어의 개념을 적절하게 정의할 수 있다는 원칙에 입각하여 본 발명의 기술적 사상에 부합하는 의미와 개념으로 해석되어야만 한다. 따라서, 본 명세서에 기재된 실시예와 도면에 도시된 구성은 본 발명의 가장 바람직한 일 실시예에 불과할 뿐이고 본 발명의 기술적 사상을 모두 대변하는 것은 아니므로, 본 출원시점에 있어서, 이들을 대체할 수 있는 다양한 균등물과 변형예들이 있을 수 있음을 이해하여야 한다.Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings. Prior to this, terms and words used in the present specification and claims should not be construed in a conventional or dictionary sense, and the inventor can properly define the concept of a term to describe its invention in the best way possible It should be construed as meaning and concept consistent with the technical idea of the present invention. Therefore, the embodiments described in the present specification and the configurations shown in the drawings are only the most preferred embodiments of the present invention and do not represent all the technical ideas of the present invention. Therefore, at the time of the present application, It should be understood that various equivalents and modifications may be present.

도 2는 본 발명에 따른 해상에 위치한 원전의 비상냉각 시스템의 개략적 구조를 도시한 도면이다.Fig. 2 is a diagram showing the schematic structure of an emergency cooling system of a nuclear power plant located in the sea according to the present invention.

거대한 구조물 자체의 중력에 의해 발생하는 중량으로 구조물의 안정성을 확보하는 구조물의 형태를 GBS(gravity-based-structure)라 하며, GBS는 주로 강과 철근콘크리트를 사용하여 시공이 되며 해양 플랜트 건설에 사용된다. GBS구조물 제작 완료 후, 터크보트등을 사용하여 설치 목표지점까지 인양하며 발라스팅 시스템을 사용하여 바다 바닥에 착저하게 된다.GBS (gravity-based-structure) is a type of structure that secures the stability of a structure by the gravity generated by the gravity of a huge structure itself. GBS is mainly used with steel and reinforced concrete and is used for construction of an offshore plant . After the GBS structure is completed, it is lifted to the installation target point using a turbo boat, and the ballasting system is used to set it on the sea floor.

먼저 도 2에 도시된 바와 같이 본 발명에 따른 해상에 위치한 원전의 비상냉각 시스템은 해수(Seawater)가 해수 파이프 라인(11)을 통하여 연결되어 있어 충분한 양의 냉각수를 바다로부터 지속적으로 공급받는 발라스팅 탱크(10)와, 상기 발라스팅 탱크(10)에 유입된 해수를 비상 냉각수로 이용하여 원자로 내부의 온도와 압력을 낮추는 EPCCS(Emergence Passive Containment Cooling System)(20)와, 상기 발라스팅 탱크(10)에 유입된 해수를 비상 냉각수로 이용하여 반응로(reactor) 내부의 온도와 압력을 낮추는 EPRVCS(Emergence Passive Reactor Vessel Cooling System)(30)로 구성된다.As shown in FIG. 2, the emergency cooling system of a nuclear power plant located at the sea according to the present invention is a system in which a seawater is connected through a seawater pipeline 11 so that a sufficient amount of cooling water is continuously supplied from the sea, An EPCCS (Emergence Passive Containment Cooling System) 20 for lowering the temperature and pressure inside the reactor by using seawater introduced into the ballasting tank 10 as emergency cooling water, a ballast tank 10 And an EPRVCS (Emergence Passive Reactor Vessel Cooling System) 30 for reducing the temperature and pressure inside the reactor using the seawater introduced into the reactor as emergency cooling water.

상기 EPCCS(Emergence Passive Containment Cooling System)(20)와EPRVCS(Emergence Passive Reactor Vessel Cooling System)(30)는 도 1의 육상원전 비상냉각 시스템의 부가적인 시스템이며, 초과 설계기준사고(BDBY: Beyond Design Basic Accident) 시 작동하게 된다.The EPCCS (Emergency Passive Containment Cooling System) 20 and the EPRVCS (Emergency Passive Reactor Vessel Cooling System) 30 are additional systems of the onshore nuclear emergency cooling system of FIG. 1, Accident).

즉, 평상시 냉각 시스템인 ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)과 함께 작동할 수도 있으며, 상기 ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)이 작동하지 않을 때도 작동한다.In other words, it may operate in conjunction with an ordinary cooling system ECCS (Emergency Core Cooling System), a CSS (Containment Spray System), and an IVR (In-Vessel Retention). The ECCS (Emergency Core Cooling System), CSS (Containment Spray System) , And when IVR (In-Vessel Retention) does not work.

상기 EPCCS(Emergence Passive Containment Cooling System)(20)와EPRVCS(Emergence Passive Reactor Vessel Cooling System)(30)는 상기 발라스팅 탱크(10) 내부의 발라스팅 워터(12)를 냉각수로 사용한다.The EPCCS (Emergency Passive Containment Cooling System) 20 and the EPRVCS (Emergency Passive Reactor Vessel Cooling System) 30 use the ballasting water 12 in the ballasting tank 10 as cooling water.

상기 EPCCS(Emergence Passive Containment Cooling System)(20)는 원자로 내부에 설치된 열 교환기(heat exchanger)(21)와 상기 발라스팅 탱크(10)의 발라스팅 워터(12)를 상기 열 교환기(heat exchanger)(21)에 공급하는 발라스트 워터 파이프 라인(22)과, 상기 열 교환기(21)부터 발생되는 스팀을 상기 발라스팅 탱크에 전달하는 스팀 전달 파이프 라인(23)과, 원자로(Containment building) 내부와 상기 발라스팅 탱크(10 사이에 원자로 내부의 압력 및 온도를 상쇄시키는 필터링부(24)로 구성된다.The Emergence Passive Containment Cooling System (EPCCS) 20 includes a heat exchanger 21 installed in the reactor and a ballasting water 12 of the ballasting tank 10 to the heat exchanger A steam delivery pipeline 23 for delivering the steam generated from the heat exchanger 21 to the ballasting tank 22 and the inside of the reactor vessel 21 and the ballast water pipeline 22 for supplying the steam generated from the heat exchanger 21 to the ballasting tank 21, And a filtering unit 24 for canceling the pressure and temperature inside the reactor between the stinging tanks 10.

여기서, 상기 EPCCS(Emergence Passive Containment Cooling System)(20)는 냉각재 상실 사고 등의 이유로 인해 원자로 계통 내부의 높은 온도 압력의 물이 원자로(Containment Building) 내부로 방출되고 소외전원이 차단되거나 비상디젤발전기 작동이 멈추어서, 핵분열 반응이 정지된반응로(reactor)에서의 붕괴열이 지속적으로 원자로 내부의 압력 및 온도를 상승시키게 될 경우 작동한다.In the EPCCS (Emergency Passive Containment Cooling System) 20, water having a high temperature and pressure inside the reactor system is discharged into a containment building due to a loss of coolant, And stops when the decay heat in the reactor in which the fission reaction is stopped causes the pressure and temperature inside the reactor to be continuously increased.

그리고, 상기 열 교환기(Heat exchanger)(21)는 원자로((Containment Building) 내부에 위치시켜, 열 교환을 통해 열을 제거하며, 이때 상기 발라스팅 탱크(10)의 발라스팅 워터(12)를 냉각수로 사용한다.The heat exchanger 21 is disposed inside a reactor container to remove heat through heat exchange and the ballasting water 12 of the ballasting tank 10 is introduced into the cooling water .

이때, 상기 발라스팅 워터(12)는 발라스팅 탱크(10), 발라스트 워터 파이프 라인(22), 열 교환기(21), 스팀 전달 파이프 라인(23) 또는 필터링부(24)에서 발라스팅 탱크(10)로 순환한다.At this time, the ballasting water 12 is supplied to the ballasting tank 10, the ballast water pipeline 22, the heat exchanger 21, the steam transfer pipeline 23, or the filtering unit 24, ).

또한 상기 발라스팅 워터(12)인 냉각수는 수두 차를 통해 순환하므로 상기 열 교환기(21) 및 발라스트 파이프 라인(22), 스팀 전달 파이프 라인(23), 필터링부(24)는 상기 발라스팅 워터(12)의 자유수면의 높이보다 낮다.Since the cooling water as the ballasting water 12 circulates through the water head difference, the heat exchanger 21 and the ballast pipeline 22, the steam delivery pipeline 23 and the filtering unit 24 are connected to the ballasting water 12). ≪ / RTI >

즉, 상기 발라스팅 탱크(10)속의 발라스팅 워터(12)는 응축기의 역할을 하며, 최종 열침원이 된다.That is, the ballasting water 12 in the ballasting tank 10 functions as a condenser and becomes a final heat sink.

그리고, 상기 발라스팅 탱크(10) 내부의 온도 및 압력을 낮게 유지하기 위하여 피동 밸브(Passive valve)(13)를 두어 스팀 배출 및 발라스팅 탱크(10) 내부의 온도 및 기압을 낮추도록 한다.A passive valve 13 is installed to lower the temperature and the pressure inside the steam discharging and ballasting tank 10 in order to keep the temperature and the pressure inside the ballasting tank 10 low.

상기 EPRVCS(Emergency Passive Reactor Vessel Cooling System)(30)는 IVR(In-Vessel Retention)의 보조 시스템으로 소외전원 및 비상디젤전기가 작동되지 않아 반응로(reactor)(40) 내부의 온도와 압력이 상승할 때 작동되며, 반응로(reactor)(40)에 연결되어 상기 발라스팅 탱크(10)의 비상 냉각수가 유입되는 반응조 리텐션 파이프 라인(31)를 포함한다.The EPRVCS (Emergency Passive Reactor Vessel Cooling System) 30 is an auxiliary system of IVR (In-Vessel Retention), and the off-line power supply and the emergency diesel electric power are not operated and the temperature and pressure inside the reactor 40 rise And a reaction tank retention pipeline 31 which is connected to a reactor 40 and into which the emergency cooling water of the ballasting tank 10 flows.

상기 발라스팅 탱크(10)속의 발라스팅 워터(12)는 상기 반응조 리텐션 파이프 라인(31)를 통해 반응로(40) 벽에 전달되어 반응로(40) 내부의 온도와 압력을 낮추게 된다.The ballasting water 12 in the ballasting tank 10 is transferred to the wall of the reactor 40 through the reactor retention pipeline 31 to lower the temperature and the pressure inside the reactor 40.

이때, 생성되는 스팀은 상기 EPCCS(Emergence Passive Containment Cooling System)(20)를 통해 응축되어 IRWST((In-containment Refueling Water Storage Tank)(50)에 저장된다.At this time, the generated steam is condensed through the EPCCS (Emergency Passive Containment Cooling System) 20 and stored in the IRWST (In-containment Refueling Water Storage Tank) 50.

즉, 원자로(Containment building) 내부의 온도 및 압력 상승은 상기 EPCCS(Emergence Passive Containment Cooling System)(20)를 통해 제거되어 상기 EPRVCS(Emergency Passive Reactor Vessel Cooling System)(30)에 냉각수가 주입될 수 있도록 압력과 온도를 낮추어 수두 차를 지속적으로 유지할 수 있게 한다.That is, the temperature and pressure rise inside the containment building is removed through the EPCCS (Emergency Passive Containment Cooling System) 20 and the cooling water is injected into the EPRVCS (Emergency Passive Reactor Vessel Cooling System) The pressure and temperature can be lowered to keep the head difference constant.

여기서 상기 냉각수인 발라스팅 워터(12)는 수두 차로 주입되므로 반응로(40) 및 주변장치의 위치는 항상 상기 발라스팅 워터(12)의 자유수면 높이보다 낮아야 한다.Here, since the cooling water ballasting water 12 is injected with the water head difference, the position of the reactor 40 and the peripheral device must always be lower than the free water surface height of the ballasting water 12.

도 3은 본 발명에 따른 해양원전 비상냉각 시스템을 다수개로 구성한 도면으로, 도 2에 따른 상기 발라스팅 탱크(10), 발라스트 워터 파이프 라인(22), 열 교환기(21), 스팀 전달 파이프 라인(23), 필터링부(24)를 다수개 설치하므로 열 교환 및 효율을 높인다.FIG. 3 is a view showing a plurality of marine nuclear reactor emergency cooling systems according to the present invention, and includes the ballasting tank 10, the ballast water pipeline 22, the heat exchanger 21, the steam delivery pipeline (FIG. 23, and a plurality of filtering units 24 are installed to increase heat exchange efficiency.

또한 상기 반응조 리텐션 파이프 라인(31)도 다수개 구성하므로 냉각수 주입량 및 속도를 증가시킴으로써 충분한 냉각수를 공급한다.In addition, since a plurality of the reactor retention pipelines 31 are also provided, sufficient cooling water is supplied by increasing the injection amount and speed of the cooling water.

10: 발라스팅 탱크 11: 파이프
12: 발라스팅 워터 13: 피동 밸브
20: EPCCS 21: 열 교환기
22: 발라스트 워터 파이프 라인 23: 스팀 전달 파이프 라인
24: 필터링부 30: EPRVCS
31: 반응조 리텐션 파이프 라인 40: 반응로(reactor)
50: IRWST10: ballasting tank 11: pipe
12: Ballasting water 13: Piston valve
20: EPCCS 21: Heat exchanger
22: Ballast Water Pipeline 23: Steam Propulsion Pipeline
24: Filtering unit 30: EPRVCS
31: Reactor Retention Pipeline 40: Reactor
50: IRWST

Claims (10)

ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)로 이루어진 원전의 능동(Active) 비상냉각 시스템을 포함하여,
해수와 연결된 발라스팅 탱크와;
상기 발라스팅 탱크에 유입된 해수를 비상 냉각수로 이용하여 원자로 내부의 온도와 압력을 낮추는 EPCCS(Emergence Passive Containment Cooling System)와;
상기 발라스팅 탱크에 유입된 해수를 비상 냉각수로 이용하여 반응로(reactor) 내부의 온도와 압력을 낮추는 EPRVCS(Emergence Passive Reactor Vessel Cooling System)
를 포함하는 것을 특징으로 하는 해양원전 비상냉각 시스템.
Including nuclear active emergency cooling systems consisting of ECCS (Emergency Core Cooling System), CSS (Containment Spray System) and IVR (In-Vessel Retention)
A ballast tank connected to seawater;
An EPCCS (Emergency Passive Containment Cooling System) that uses the seawater introduced into the ballasting tank as emergency cooling water to lower the temperature and pressure inside the reactor;
(Emergence Passive Reactor Vessel Cooling System) EPRVCS (Emergency Passive Reactor Vessel Cooling System) which uses the seawater introduced into the ballasting tank as emergency cooling water to lower the temperature and pressure inside the reactor,
And an emergency cooling system for the marine nuclear power plant.
제 1 항에 있어서,
상기 EPCCS(Emergency Passive Containment Cooling System)는,
원자로 내부에 설치되는 열 교환기(heat exchanger)와;
상기 열 교환기에 상기 발라스팅 탱크의 비상 냉각수를 공급하는 발라스트 워터 파이프 라인과;
상기 열 교환기부터 발생되는 스팀을 상기 발라스팅 탱크에 전달하는 스팀 전달 파이프 라인
을 포함하는 것을 특징으로 하는 해양원전 비상냉각 시스템.
The method according to claim 1,
The EPCCS (Emergency Passive Containment Cooling System)
A heat exchanger installed inside the reactor;
A ballast water pipeline for supplying emergency cooling water of the ballasting tank to the heat exchanger;
A steam delivery pipe for delivering steam generated from the heat exchanger to the ballast tank
And an emergency cooling system for the marine nuclear power plant.
제 1 항에 있어서,
상기 EPCCS(Emergency Passive Containment Cooling system)는
원자로 내부와 상기 발라스팅 탱크 사이에 원자로 내부의 압력 및 온도를 상쇄시키는 필터링부
를 포함하는 것을 특징으로 하는 해양원전 비상냉각 시스템.
The method according to claim 1,
The EPCCS (Emergency Passive Containment Cooling system)
A filtering unit for canceling the pressure and the temperature inside the reactor between the inside of the reactor and the ballasting tank;
And an emergency cooling system for the marine nuclear power plant.
제 2 항 또는 제 3 항에 있어서,
상기 열 교환기 및 발라스트 워터 파이프 라인과 스팀 전달 파이프 라인, 필터링부는 상기 냉각수의 자유수면의 높이보다 낮은 것
을 특징으로 하는 해양원전 비상냉각 시스템.
The method according to claim 2 or 3,
The heat exchanger, the ballast water pipeline, the steam delivery pipeline, and the filtering section are lower than the height of the free water surface of the cooling water
Wherein the cooling system comprises:
제 1 항에 있어서,
상기 발라스팅 탱크는,
상기 발라스팅 탱크 내부의 스팀 배출과 내부의 온도 및 기압을 낮추는 피동 밸브
를 포함하는 것을 특징으로 하는 해양원전 비상냉각 시스템.
The method according to claim 1,
The ballasting tank may include:
A discharge valve for lowering the temperature and the pressure of the inside of the ballasting tank;
And an emergency cooling system for the marine nuclear power plant.
제 1 항에 있어서,
상기 EPRVCS(Emergency Passive Reactor Vessel Cooling System)는
반응로(reactor)에 연결되어 상기 발라스팅 탱크의 비상 냉각수가 유입되는 반응조 리텐션 파이프 라인
를 포함하는 것을 특징으로 하는 해양원전 비상냉각 시스템.
The method according to claim 1,
The EPRVCS (Emergency Passive Reactor Vessel Cooling System)
A reaction tank retention pipe connected to a reactor and into which the emergency cooling water of the ballasting tank flows,
And an emergency cooling system for the marine nuclear power plant.
제 6항에 있어서,
상기 반응로에서 생성되는 스팀은 상기 EPCCS를 통해 응축되어 IRWST(In-containment Refueling Water Storage Tank)에 저장되는 것
을 특징으로 하는 해양원전 비상냉각 시스템.
The method according to claim 6,
The steam generated in the reactor is condensed through the EPCCS and stored in an IRWST (In-containment Refueling Water Storage Tank)
Wherein the cooling system comprises:
제 6항에 있어서,
상기 반응로 및 반응조 리텐션 파이프 라인은 냉각수의 자유수면 높이 보다 낮은 것
을 특징으로 하는 해양원전 비상냉각 시스템.
The method according to claim 6,
The reactor and the reaction tank retention pipeline are lower than the free water surface height of the cooling water
Wherein the cooling system comprises:
ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)로 이루어진 원전의 능동(Active) 비상냉각 시스템의 작동 유무와 관계없이,
발라스팅 탱크에 유입된 비상 냉각수를 원자로 내부의 열 교환기(heat exchanger)에 공급하는 단계와;
상기 공급된 비상 냉각수를 통하여 냉각된 열 교환기의 스팀을 발라스팅 탱크에 배출하는 단계
를 포함하는 것을 특징으로 하는 해양원전 비상냉각 방법.
Regardless of whether the active emergency cooling system of the nuclear power plant is composed of ECCS (Emergency Core Cooling System), CSS (Containment Spray System) and IVR (In-Vessel Retention)
Supplying the emergency cooling water introduced into the ballasting tank to a heat exchanger inside the reactor;
Discharging the steam of the heat exchanger cooled through the supplied emergency cooling water to the ballasting tank
Wherein the cooling of the nuclear reactor emergency cooling system comprises:
ECCS(Emergence Core Cooling System), CSS(Containment Spray System), IVR(In-Vessel Retention)로 이루어진 원전의 능동(Active) 비상냉각 시스템의 작동 유무와 관계없이,
상기 발라스팅 탱크에 유입된 비상 냉각수가 반응로에 유입되는 단계와;
상기 유입된 비상 냉각수에 의해 반응로가 냉각되는 단계
를 포함하는 것을 특징으로 하는 해양원전 비상냉각 방법.Regardless of whether the active emergency cooling system of the nuclear power plant is composed of ECCS (Emergency Core Cooling System), CSS (Containment Spray System) and IVR (In-Vessel Retention)
The emergency cooling water flowing into the ballasting tank flows into the reactor;
And cooling the reactor by the introduced emergency cooling water
Wherein the cooling of the nuclear reactor emergency cooling system comprises:
KR20130040137A 2013-04-11 2013-04-11 Cooling system for nuclear power plant by using water KR20140122979A (en)

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Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104979025A (en) * 2015-06-30 2015-10-14 浙江工业大学 Platform for testing structural integrity of reactor pressure vessel under IVR condition
CN105513653A (en) * 2016-02-01 2016-04-20 西南石油大学 Degassing device for natural circulation and forced circulation experiment loops and degassing method thereof
CN106251916A (en) * 2016-08-31 2016-12-21 长江勘测规划设计研究有限责任公司 A kind of underground nuclear power station cavern type double containment
CN112768095A (en) * 2021-01-25 2021-05-07 中国船舶重工集团公司第七一九研究所 Containment shielding and cooling system for marine nuclear power platform
KR20210125204A (en) * 2020-04-08 2021-10-18 한국원자력연구원 Passive Colling System for Nuclear Reactor having Anti-Sticking System for Shell and Method for Operating the Same
KR20220029928A (en) * 2020-09-02 2022-03-10 한국원자력연구원 Passive cooling installation of atomic reactor and passive cooling method thereof

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104979025A (en) * 2015-06-30 2015-10-14 浙江工业大学 Platform for testing structural integrity of reactor pressure vessel under IVR condition
CN105513653A (en) * 2016-02-01 2016-04-20 西南石油大学 Degassing device for natural circulation and forced circulation experiment loops and degassing method thereof
CN106251916A (en) * 2016-08-31 2016-12-21 长江勘测规划设计研究有限责任公司 A kind of underground nuclear power station cavern type double containment
CN106251916B (en) * 2016-08-31 2018-01-23 长江勘测规划设计研究有限责任公司 A kind of underground nuclear power station cavern type double containment
KR20210125204A (en) * 2020-04-08 2021-10-18 한국원자력연구원 Passive Colling System for Nuclear Reactor having Anti-Sticking System for Shell and Method for Operating the Same
KR20220029928A (en) * 2020-09-02 2022-03-10 한국원자력연구원 Passive cooling installation of atomic reactor and passive cooling method thereof
CN112768095A (en) * 2021-01-25 2021-05-07 中国船舶重工集团公司第七一九研究所 Containment shielding and cooling system for marine nuclear power platform

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