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KR20160118537A - Passive Safety System of Nuclear Power generation system - Google Patents

Passive Safety System of Nuclear Power generation system Download PDF

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Publication number
KR20160118537A
KR20160118537A KR1020150046809A KR20150046809A KR20160118537A KR 20160118537 A KR20160118537 A KR 20160118537A KR 1020150046809 A KR1020150046809 A KR 1020150046809A KR 20150046809 A KR20150046809 A KR 20150046809A KR 20160118537 A KR20160118537 A KR 20160118537A
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steam generator
water
auxiliary steam
passive
reactor
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Korean (ko)
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김영선
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김영선
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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
    • 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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  • 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

The present invention relates to a passive safety system which can stably eliminate residual heat, generated in a nuclear reactor, even in case of a natural disaster such as an earthquake, a tsunami and the like or an emergency situation where a problem occurs in a nuclear power generation station power system by intended terror in a nuclear power generation system.

Description

원자력발전시스템의 피동안전계통 {Passive Safety System of Nuclear Power generation system}{Passive Safety System of Nuclear Power Generation System}

본 발명은 자연재해나 인재에 의해 원자력발전시스템 전력계통에 문제가 발생하여, 원자력발전시스템이 정지 되면서, 원자로에서 발생되는 잔열을 제거하지 못해 발생하는 사고를 예방하기 위한 피동안전계통에 관한 것이다.
The present invention relates to a passive safety system for preventing an accident caused by a failure of a nuclear power generation system due to a problem of a power system of a nuclear power generation system due to a natural disaster or a human resource and failing to remove residual heat generated in the reactor.

일반적으로 원자력발전소는 전력을 생산하는 과정에서 방사성 물질이 비정상적으로 누출되는 사고가 발생하면 그 피해가 엄청나기 때문에 안정성 설계가 매우 중요하다.
In general, safety design is very important because nuclear power plants suffer from damage caused by abnormal leakage of radioactive materials during power generation.

상기와 같은 사고는 해일이나 지진 등의 자연재해나 운전자의 실수, 펌프의 오작동, 전력선 계통에 문제 등에 의해 악화된다.
Such accidents are exacerbated by natural disasters such as tsunamis or earthquakes, mistakes by drivers, malfunctions of pumps, problems with power line systems, and the like.

위와 같은 사고 발생시, 안정성 설계를 위해서는 외부 동력의 공급수단에 의존하지 않고 중력과 자연순환 응축, 비등 등의 자연현상을 활용하여 원자로의 안정성을 담보하려는 것이 일반적이다.
In case of such an accident, it is general to secure stability of reactor by utilizing natural phenomenon such as gravity, natural circulation condensation, boiling, etc., without depending on external power supply means for stability design.

이러한 문제점을 해결하기 위해 원자로 사고시에 증기발생기의 이차측에서 발생하는 증기를 응축하여 원자로 잔열을 피동적으로 냉각하여 원자력발전소의 안정성과 경제성을 높일 수 있는 피동형 이차 응축계통의 개념이 제안되고 있다.
To solve these problems, a concept of a passive secondary condensation system has been proposed in which steam generated from a secondary side of a steam generator during a reactor accident is condensed to passively cool the residual heat of the nuclear reactor, thereby enhancing the stability and economy of the nuclear power plant.

공개된 기술로는 “주증기를 이용한 증기발생기 피동급수 계통의 열중격방지 열교환장치” (국내공개특허 2014-0032139호)와, “피동보조 급수계통을 이용한 경수로의 응급잔열제거 및 격납용기 냉각계통”(국내특허 10-1224023), “원자력 발전소의 피동형 냉각시스템”(국내특허 10-1229954), “안전보호용기를 구비한 피동형 비상노심냉각설비 및 이를 이용한 열전달 증가방법”(국내공개특허 2013-0000572), “원자로의 다목적 냉각장치”(국내특허 10-1302749), “가압경수로의 피동형 원자로 및 격납용기 응축시스템”(국내공개특허 2013-0129606) 등이 개시되어 있다.
The disclosed technologies are disclosed in Korean Patent Laid-Open Publication No. 2014-0032139, entitled " Preheating Heat Prevention Device for Steam Generator Driven Feeding System Using Main Steam " (Korean Patent Publication No. 2014-0032139) (Domestic Patent 10-1224023), "Passive Cooling System of Nuclear Power Plant" (Korean Patent No. 10-1229954), "Passive Emergency Core Cooling System Having Safety Protection Container and Method of Increasing Heat Transfer Using It" No. 10-1302749), "Passive Reactor and Storage Container Condensation System of Pressurized Light Water Reactor" (Korean Patent Laid-Open Publication No. 2013-0129606), etc. are disclosed.

그러나, 상기 피동형 응축계통 기술들의 공통된 근본적인 문제점은 피동응축냉각탱크의 냉각수량에 의해 원자로 잔열제거 가능시간이 제한된다는 점과, 중력낙차에 의해 냉각수를 순환하기 위해 피동응축냉각탱크가 원자로나 증기발생기보다 높은 곳에 위치해야 하기 때문에 건설비용이 많이 들어 경제성에 문제가 발생한다.
However, a common fundamental problem of the above-mentioned passive condensation system technologies is that the time for removing the residual heat of the nuclear reactor is limited by the amount of cooling water in the passive condensation cooling tank and that the passive condensation cooling tank is a reactor or steam generator Because it is required to be located at a higher level, construction cost is high and economic problems arise.

피동형 응축계통을 갖춘 원자로 중 설계검증을 마치고 상용화(2015년 현재)에 들어간 원자로는 웨스팅하우스사의 가압경수로(AP1000)형 원자력발전소가 유일하나, 강철 격납 용기를 사용함으로써, 이 역시 경제성이 문제성이 있다.
Among the reactors with passive condensation system, after the design verification and commercialization (as of 2015), Westinghouse's pressurized light-water reactor (AP1000) type nuclear power plant is the only one but using steel containment is also problematic in economy .

본 발명은 상기 기술한 바와 같이 중력낙차에 의해 자연순환 방식으로 주증기를 순환하는 방법은,
As described above, according to the present invention, a method of circulating a main steam in a natural circulation manner by a gravitational drop,

피동응축냉각탱크를 증기발생기 보다 높은 위치에 설치해야 하기 때문에, 원자력발전소를 건설하는데 막대한 비용이 발생하고, 피동응축냉각탱크 내부의 냉각수 수량을 무제한 늘리기 어렵기 때문에,
Since the passive condensation cooling tank needs to be installed at a higher position than the steam generator, there is a great cost to construct a nuclear power plant and it is difficult to increase the amount of cooling water in the passive condensation cooling tank unlimitedly,

원자력발전소 사고 발생시, 원자로에서 발생하는 응급 잔열을 제거하는데 냉각수량에 의해 응급잔열 제거시간이 제한될 수 있다.
In the event of a nuclear power plant accident, the emergency residual heat removal time may be limited by the amount of cooling water to remove the emergency residuals from the reactor.

본 발명의 피동안전계통은 자연재해나 인재에 의하여 원자력발전시스템 전원상실 사고 발생시,
The passive safety system of the present invention is a system in which when a power failure occurs in a nuclear power generation system due to a natural disaster or a human resource,

증기발생기 혹은, 원자로에서 발생하는 주증기로 부터 주증기의 열을 일부 회수하여 동력을 생산, 이 동력으로 각종 펌프를 구동하여 주증기를 계속 순환 시키면서 원자로에서 발생되는 응급 잔열을 제거할 수 있다.
Steam generated from the steam generator or main steam generated from the reactor can be partially recovered to produce power, and various pumps can be driven by this power to continuously circulate the main steam, thereby eliminating the emergency residual heat generated in the reactor.

상기 본 발명의 피동안전계통은 원자로(혹은 증기발생기)에서 생성되는 주증기로 부터 열교환기를 통해 열을 공급받아 증기를 생산하는 보조증기발생기를 구비하여, The passive safety system of the present invention includes an auxiliary steam generator for generating steam by receiving heat from a main steam generated in a reactor (or a steam generator) through a heat exchanger,

보조증기발생기에서 발생되는 증기로 주증기용 순환펌프와 피동응축냉각탱크에 외부 냉각수를 급수하는 급수펌프 등, 피동안전계통의 모든 펌프를 구동하여, 중력낙차와 같은 자연순환 방식이 아닌, 펌프에 의해 주증기를 순환시켜 원자로에서 발생되는 응급 잔열을 제거할 수 있다.
The steam generated from the auxiliary steam generator drives all the pumps of the passive safety system such as the circulation pump for the main steam and the feed pump for supplying the external cooling water to the passive condensation cooling tank, It is possible to circulate the main steam to remove the emergency residuals generated in the reactor.

중력낙차를 사용하지 않기 때문에, 피동응축냉각탱크는 지하는 지상에 설치가 가능하기 때문에 기존 원자력발전시스템도 크게 설계 변경 없이 본 발명의 피동안전계통을 설치하여 안정성을 높일 수 있다.
Since the gravity deflection is not used, the passive condensation cooling tank can be installed on the ground, so that the existing nuclear power generation system can be improved in stability by installing the passive safety system of the present invention without greatly changing the design.

따라서, 기존 원자력발전시스템이나 신규 원자력발전시스템의 안전성을 높이는 데, 종래의 피동안전계통 보다, 상대적으로 아주 적은 비용을 소요되어 원자력발전시스템의 경제성을 높일 수 있다.
Therefore, it is possible to increase the safety of the existing nuclear power generation system or the new nuclear power generation system, and it is possible to increase the economical efficiency of the nuclear power generation system by requiring a relatively small cost compared to the conventional passive safety system.

종래기술에 본 발명의 일부 기술을 적용하는 것으로도 피동응축냉각 탱크의 냉각수 용량 제한 및 응축수를 증기발생기에 공급하기 위한 중력낙차를 고려한 높은 위치에 탱크를 설치하는 문제 등을 해결하여 원자력발전시스템의 전원상실 사고등 It is possible to solve the problem of installing the tank at a high position in consideration of the limitation of the cooling water capacity of the driven condensing cooling tank and the gravity deflection for supplying the condensed water to the steam generator by applying some of the techniques of the present invention to the prior art, Power loss accident etc.

의 비상 사태에 대응할 수 있을 뿐 아니라,Not only can we cope with the emergency of

신규 원자력발전시스템 뿐아니라, 기 가동하고 있는 원자력발전시스템에도 쉽게 적용가능하여 안전성을 확보할 수 있고,
In addition to the new nuclear power generation system, it can be easily applied to the existing nuclear power generation system,

높은 비용이 소요되는 피동응축냉각계통을 적용한 원자력발전시스템 보다 훨씬 경제적인 원자력발전시스템을 건설할 수 있다.
It is possible to construct a nuclear power generation system which is much more economical than a nuclear power generation system using a high-cost passive condensation cooling system.

도1 은 종래기술의 피동보조 급수계통을 이용한 경수로의 응급잔열제거 및 격납용기 냉각계통 구성도.
도2 은 본 발명의 원자력발전시스템의 주증기를 이용한 피동안전계통도.
도3 는 본 발명의 원자력발전시스템의 주증기를 이용한 피동안전계통 또 다른 실시예.FIG. 1 is a schematic view of a system for removing emergency residual heat and a containment vessel cooling system of a light-water reactor using a driven auxiliary water supply system of the prior art. FIG.
2 is a schematic diagram of a passive safety system using a main steam of the nuclear power generation system of the present invention.
FIG. 3 is another embodiment of the passive safety system using the main steam of the nuclear power generation system of the present invention.

본 발명은 원자력발전시스템 전력계통 문제 발생시, 원자로에서 발생되는 잔열을 제거하여 후쿠시마와 같이 원자로가 녹아 내리는 재앙을 방지하기 위한 피동안전계통에 관한 것이다.
The present invention relates to a passive safety system for preventing disasters such as Fukushima from being melted down by removing residual heat generated in a nuclear reactor when a power system problem occurs in a nuclear power generation system.

도1 은 종래기술의 피동보조 급수계통을 이용한 경수로의 응급잔열제거 및 격납용기 냉각계통 구성도이다.
FIG. 1 is a configuration diagram of an emergency residual heat removal and a containment vessel cooling system of a light-water reactor using a driven auxiliary water supply system of the prior art.

이 종래기술은 상기와 같은 전력계통 문제 발생시, 증기발생기(10)으로 부터 발생되는 주증기를 주증기관(11)을 통해 응축수조(30)의 열교환기(7)를 통해 냉각수(20)로 응축시켜 중력낙차로 증기발생기(10)로 자연순환 시키는 일반적인 피동응축시스템 기술에서,
This prior art technology has been developed to condense the main steam generated from the steam generator 10 into the cooling water 20 through the heat exchanger 7 of the condensate water tank 30 through the main steam pipe 11, In a typical passive condensation system technique that allows natural circulation to the steam generator 10 with a gravity drop,

좀더 원자로에서 발생되는 응급 잔열 제거시간을 연장하기 위해, 1차측 재장전수조탱크(50)에 저장되는 있는 냉각수 더 활용하여, 재장전수조탱크(50)로 1차측에서 원자로(1)의 응급잔열을 제거하는 격납용기 피동냉각기능과 피동응축탱크(30)의 냉각수로 증기발생기(10)로 생성되는 주증기를 응축하는 피동보조급수 계통을 응축기풀(27)을 통해 열교환 하는 방법으로 1차계통과 2차계통을 통해 응급잔열을 제거하는 방법을 제시하고 있다.
It is possible to use the cooling water stored in the primary recharge water tank 50 to further increase the emergency residual capacity of the reactor 1 from the primary to the recharging water tank 50. [ And a passive auxiliary water supply system for condensing the main steam generated in the steam generator 10 by the cooling water of the passive condensation tank 30 through a condenser pool 27, And a method of removing emergency residuals through the secondary system.

그러나, 상기 방법도 여전히 재장전수조탱크(50)나 피동응축탱크(30)가 원자로(1)와 증기발생기(10)보다 높은 곳에 위치해 있어야 하고, 그런 이유로 냉각수가 제한되기 때문에, 사고시 응급잔열을 제거하는 시간이 제한된다는 문제점이 여전히 남아 있고, 많은 냉각수를 저장하는 재장전수조탱크(50)나 피동응축탱크(30)를 구비한 원자력발전소를 건설하는데 있어 많은 비용이 소요되어 경제성이 떨어질 수 밖에 없다는 것이다.
However, this method still requires that the recharging tank 50 or the driven condensing tank 30 be located higher than the reactor 1 and the steam generator 10, and therefore the cooling water is limited. There is still a problem in that the time for removal is limited and the cost of constructing the nuclear power plant having the recharge tank tank 50 or the driven condensation tank 30 for storing a lot of coolant water is high, It is not.

도2 은 본 발명의 원자력발전시스템의 주증기를 이용한 피동안전계통도 이다.
2 is a schematic diagram of a passive safety system using the main steam of the nuclear power generation system of the present invention.

본 발명은 원전 사고시, According to the present invention,

원자로의 잔열을 제거하기 위해 원자로(100)에서 발생되는 주증기를 냉각수가 충진된 피동응축 냉각탱크(200)의 피동응축열교환기(220)를 통해서 응축시켜 응축수를 중력낙차 에 의해 원자로(100)로 자연순환 시키는 피동응축시스템에서,
The main steam generated in the reactor 100 is condensed through the passive condensation heat exchanger 220 of the passive condensation cooling tank 200 filled with the cooling water to remove the residual heat of the reactor and the condensed water is discharged to the reactor 100 In a passive condensing system that spontaneously circulates,

상기 원자로(100)에서 발생되는 주증기로 부터 열교환기(212)를 통해 열을 공급받아 증기를 생산하는 보조증기발생기(210)를 더 구비하여, 중력낙차에 의한 자연순환 방식이 아닌 보조증기발생기(210)에서 생산된 증기로 냉각수펌프(224)와 급수펌프(213), 순환펌프(222)를 구동하여, 주증기를 순환시켜 원자로(100)의 잔열을 제거함을 특징으로 하는 피동안전계통에 대한 구성도 이다.
And an auxiliary steam generator 210 for generating steam by receiving heat from the main steam generated in the reactor 100 through the heat exchanger 212. The auxiliary steam generator 210, The cooling water pump 224, the water supply pump 213 and the circulation pump 222 are driven by the steam produced by the steam generator 210 to circulate the main steam to remove residual heat of the reactor 100. [ FIG.

본 발명의 상세 구성도를 살펴보면,Referring to the detailed configuration of the present invention,

원자로(100)[혹은 증기발생기, 소형원자로에서는 원자로 내부에 증기발생기가 함께 구성되어 있음], 열교환기(212), 피동응축열교환기(220), 순환펌프(222)로 폐루프를 구성하여 피동냉각계통을 구성하고 있다.
A closed loop is constituted by a reactor 100 (or a steam generator and a small reactor), a heat exchanger 212, a passive condensation heat exchanger 220 and a circulation pump 222, System.

상기 열교환기(212)는 원자로(100)에서 생성되는 주증기로 부터 열원을 흡수하여 보조증기발생기(210) 내부의 열매체인 물로 전달하는 기능을 한다.
The heat exchanger 212 absorbs the heat source from the main steam generated in the reactor 100 and transfers it to the water as the heat medium in the auxiliary steam generator 210.

원자로(100)에서 생성되는 주증기는 열교환기(212)에서 1차적으로 열을 전달하고, 피동응축열교환기(220)에서 피동응축냉각탱크(200) 내부의 냉각수와 열교환되어 응축되어, 상기 보조증기발생기(210)에서 공급하는 증기로 구동되는 순환펌프(222)에 의해 순환하면서, 원자로(100)의 응급 잔열을 제거하게 된다.
The main steam generated in the reactor 100 transfers heat primarily in the heat exchanger 212 and is heat-exchanged with the cooling water in the passive condensation cooling tank 200 in the passive condensation heat exchanger 220 to be condensed, The steam is circulated by the circulation pump 222 driven by the steam supplied from the generator 210, and the emergency residual heat of the reactor 100 is removed.

상기 보조증기발생기(210)에서 공급하는 증기는 순환펌프(222)를 구동하고 외부로 배출됨으로, 배출되는 증기량 만큼, 보조증기발생기(210) 내부로 급수펌프(213)를 통해 피동응축냉각탱크(200) 내부의 냉각수를 급수하게 된다.
The steam supplied from the auxiliary steam generator 210 drives the circulation pump 222 and is discharged to the outside of the auxiliary condenser 210 through the feed pump 213 to the passive condensation cooling tank 200). ≪ / RTI >

상기 급수펌프(213)도 보조증기발생기(210)에서 발생하는 증기에 의해 구동된다.
The water pump 213 is also driven by the steam generated in the auxiliary steam generator 210.

또한, 피동응축냉각탱크(200)의 내부로 외부의 냉각수를 급수펌프(224)를 통해 공급할 수 있다. 상기 급수펌프(213,214)를 구동한 증기도 또한 외부로 배출된다.
In addition, external cooling water can be supplied to the inside of the passive condensation cooling tank 200 through the water feed pump 224. The steam that drives the feed pumps 213 and 214 is also discharged to the outside.

도3 는 본 발명의 원자력발전시스템의 주증기를 이용한 피동안전계통 또 다른 실시 예이다.
3 is another embodiment of the passive safety system using the main steam of the nuclear power generation system of the present invention.

본 발명의 피동안전계통은 주증기로 부터 열원을 공급받아 급수펌프(224)와 순환펌프(214,222)를 구동하여, 주증기를 순환하여 원자로(100)의 응급 잔열을 제거하는 방법은 상기 도2에 도시된 바와 같이 유사하나,
The passive safety system of the present invention is a method of removing the emergency residual heat of the reactor 100 by circulating the main steam by supplying the heat source from the main steam and driving the feed pump 224 and the circulation pumps 214 and 222, As shown in Fig.

차이점은,The difference is,

보조증기발생기(210) 내부의 열매체인 물을 증발, 팽창, 응축, 압축의 랭킨사이클로 구성하여 순환한다는 점이 다르다.
Except that the water as the heat medium in the auxiliary steam generator 210 is circulated in a Rankine cycle of evaporation, expansion, condensation and compression.

주증기를 열원으로 급수펌프(224)와 순환펌프(214, 222)를 구동하기 위한 증기를 발생시키고 순환시키는 사이클은, 보조증기발생기(210), 주증기용 순환펌프(222), 보조증기 응축열교환기(216), 보조증기용 순환펌프(214)로 폐루프를 형성하여 구성된다. The cycle for generating and circulating the steam for driving the main steam to the feed pump 224 and the circulation pumps 214 and 222 is an auxiliary steam generator 210, a main steam circulation pump 222, an auxiliary steam condensing heat exchanger (216), and a circulation pump (214) for auxiliary steam.

상기와 같이 보조증기발생기(210)를 위한 랭킨사이클을 구성하면, 보조증기발생기(210) 내부의 열매체인 물을 순환시키기 때문에 급수펌프를 통해 보충수 급수가 필요 없어진다.
When the Rankine cycle for the auxiliary steam generator 210 is constructed as described above, water as a heat medium in the auxiliary steam generator 210 is circulated, and thus replenishment water supply is not necessary through the water supply pump.

또한, 상기와 같이 보조증기발생기(210)로 사이클을 구성하여 피동응축냉각탱크(200) 내부에 설치하면, 보조증기 응축열교환기(216)는 피동응축냉각탱크(200) 내부의 냉각수와 바로 열교환 할 수 있어, 별도의 외부 냉각수를 필요로 하지 않아, 간단하게 피동안전계통을 설계할 수 있다.
When the cycle is constituted by the auxiliary steam generator 210 and installed in the passive condensation cooling tank 200 as described above, the auxiliary steam condensation heat exchanger 216 performs heat exchange with the cooling water in the passive condensation cooling tank 200 It is possible to design a passive safety system simply because no separate external cooling water is required.

상기 본 발명의 피동안전계통은 중력낙차에 의한 자연순환이 아닌, 주증기로 부터 열을 공급받아, 그 열로 펌프 구동용 증기를 생산하여, 펌프를 구동하여 사이클을 구성하여 원자로(100)의 잔열을 제거함으로, 원자로(100) 보다 높은 위치에 피동응축냉각탱크(200)를 위치시킬 필요가 없어져, 지하나, 지상에 피동안전계통을 설계할 수 있어, 원자력발전소 건설비용이 낮게 소요되어, 기존 피동안전계통보다 훨씬 경제성의 우위를 점할 수 있다.
In the passive safety system of the present invention, the heat is supplied from the main steam, not the natural circulation due to the gravitational drop, the steam for pump driving is produced by the heat, the pump is driven to constitute a cycle, It is not necessary to place the passive condensation cooling tank 200 at a position higher than the reactor 100 and the passive safety system can be designed on the ground or the ground so that the construction cost of the nuclear power plant is lowered, It is possible to obtain a more economical advantage over the passive safety system.

또한, 기존 운영중인 원자력발전시스템의 안전설계를 위해 기존 시설을 그대로 두고 상기 피동안전계통을 설비할 수 있기 때문에, 기존 피동안전계통으로는 적용하기 어려운 운영중인 원자력발전시스템에도 본 발명의 피동안정계통을 설비할 수 있어, 기존 운영중인 원자력발전시스템의 안전도도 높일 수 있다.
In addition, since the above-mentioned passive safety system can be installed with the existing facility as it is for the safety design of the existing operating nuclear power generation system, the passive safety system of the present invention, which is difficult to apply to the existing passive safety system, And the safety of existing nuclear power generation systems can be increased.

100 : 원자로(혹은 증기발생기, 소형원전의 경우 원자로 내부에 증기발생기 내장)
110 : 주증기관
120 : 응축수회수관
200 : 피동응축냉각탱크
220 : 피동응축열교환기
210 : 보조증기발생기
212 : 열교환기
214, 222 : 순환펌프
216 : 보조증기 응축열교환기
213,224 : 급수펌프 100: reactor (or steam generator, in the case of a small nuclear power plant, a steam generator is built into the reactor)
110:
120: Condensate recovery pipe
200: Passive condensation cooling tank
220: Passive condensation heat exchanger
210: auxiliary steam generator
212: heat exchanger
214, 222: circulation pump
216: auxiliary steam condensing heat exchanger
213,224: Feed pump

Claims (5)

원전 사고시, 원자로의 잔열을 제거하기 위해 원자로에서 발생되는 주증기를 냉각수가 충진된 피동응축냉각탱크의 피동응축열교환기를 통해서 응축시켜 응축수를 중력낙차 에 의해 원자로로 자연순환 시키는 피동응축시스템에서,

상기 원자로에서 발생되는 주증기로 부터 열교환기를 통해 열을 공급받아 증기를 생산하는 보조증기발생기를 더 구비하여, 중력낙차에 의한 자연순환 방식이 아닌 보조증기발생기에서 생산된 증기로 급수펌프와 순환펌프를 구동하여 주증기를 순환시켜 원자로의 잔열을 제거함을 특징으로 하는 피동안전계통.
In a passive condensation system where the main steam generated from the reactor is condensed through a passive condensation heat exchanger of a passive condensation cooling tank filled with cooling water and the condensed water is spontaneously circulated to the reactor by the gravity drop to remove the residual heat of the reactor,

Further comprising an auxiliary steam generator for generating steam by receiving heat from the main steam generated from the reactor through a heat exchanger, wherein the steam generated by the auxiliary steam generator, which is not a natural circulation system due to gravity drop, Wherein the main steam is circulated to remove the residual heat of the reactor.
청구항 1항에 있어서,
보조증기발생기에서 생성된 증기가 급수펌프와 순환펌프를 구동하고 외부로 배출되면서, 보조증기발생기 내부에 충진된 물의 양이 감소된 만큼, 계속해서 상기 급수펌프에 의해 보조증기발생기 내부로 보충수를 급수함을 특징으로 하는 피동안전계통.
The method according to claim 1,
The steam generated from the auxiliary steam generator drives the water supply pump and the circulation pump and is discharged to the outside so that the amount of water filled in the auxiliary steam generator is reduced so that the supply water is continuously supplied to the auxiliary steam generator by the water supply pump Passive safety system featuring a water tank.
청구항 1항에 있어서,
보조증기발생기, 주증기용 순환펌프, 보조증기 응축열교환기, 보조증기용 순환펌프로 폐루프를 구성하여 랭킨사이클을 구성함으로서,

상기 사이클에 의해 보조증기발생기에서 발생되는 증기를 계속 순환시키면서 증기동력을 생산하여, 급수펌프와 순환펌프의 동력을 제공함을 특징으로 하는 피동안전계통.
The method according to claim 1,
By constituting the closed loop with the auxiliary steam generator, the main steam circulation pump, the auxiliary steam condensation heat exchanger and the auxiliary steam circulation pump to constitute the Rankine cycle,

Wherein steam is generated by continuously circulating the steam generated in the auxiliary steam generator by the cycle to provide the power of the water supply pump and the circulation pump.
청구항 2항에 있어서,
보조증기발생기와 보조증기발생기 내부로 보충수를 공급하는 급수펌프가 피동응축냉각탱크 내부에 설치되어,

피동응축냉각탱크 내부 냉각수를 상기 급수펌프에 의해 보조증기발생기로 급수함을 특징으로 하는 피동안전계통.
The method according to claim 2,
A feed pump for supplying supplemental water into the auxiliary steam generator and the auxiliary steam generator is installed inside the passive condensation cooling tank,

Wherein the cooling water in the passive condensation cooling tank is supplied to the auxiliary steam generator by the water supply pump.
청구항 3항에 있어서,
보조증기 응축열교환기가 피동응축냉각탱크 내부에 설치되어,
보조증기발생기로부터 생성된 증기가 보조증기 응축열교환기에서 피동응축냉각탱크 내부 냉각수에 의해 응축되어 순환됨을 특징으로 하는 피동안전계통.
The method according to claim 3,
An auxiliary steam condensing heat exchanger is installed inside the passive condensation cooling tank,
Wherein the steam generated from the auxiliary steam generator is condensed and circulated in the auxiliary steam condensing heat exchanger by the cooling water in the passive condensation cooling tank.
KR1020150046809A 2015-04-02 2015-04-02 Passive Safety System of Nuclear Power generation system KR20160118537A (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2022019559A1 (en) * 2020-07-23 2022-01-27 한국수력원자력 주식회사 Passive condensation tank cooling system of passive auxiliary feedwater system

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2022019559A1 (en) * 2020-07-23 2022-01-27 한국수력원자력 주식회사 Passive condensation tank cooling system of passive auxiliary feedwater system

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