KR20140061846A - Passive secondary condensing system of an atomic power plant - Google Patents

Passive secondary condensing system of an atomic power plant Download PDF

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KR20140061846A
KR20140061846A KR1020120128963A KR20120128963A KR20140061846A KR 20140061846 A KR20140061846 A KR 20140061846A KR 1020120128963 A KR1020120128963 A KR 1020120128963A KR 20120128963 A KR20120128963 A KR 20120128963A KR 20140061846 A KR20140061846 A KR 20140061846A
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steam
cooling water
cooling
water
passive
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KR101405666B1 (en
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김태준
유성창
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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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/26—Steam-separating arrangements
    • F22B37/268—Steam-separating arrangements specially adapted for steam generators of nuclear power plants
    • 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)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The present invention relates to a passive secondary condensation system for a nuclear power plant. More specifically, the system includes: a steam supply pipe which is branched from a main steam pipe for transferring steam generated by a steam generator to a turbine; a passive condensation cooling tank which is connected to the steam supply pipe, receives steam from the steam supply pipe in case a nuclear reactor malfunctions, and condenses the received steam; a condensation water collection pipe which is connected to the passive condensation cooling tank, receives condensed cooling water from the passive condensation cooling tank, and supplies the condensed cooling water to a main water supply pipe; and the main water supply pipe which is connected to the condensation water collection pipe, receives the condensed cooling water from the condensation water collection pipe, and supplies the condensed cooling water to the steam generator. The passive condensation cooling tank includes: a condenser which condenses the steam supplied from the steam supply pipe; and a cooling water circulation member which circulates the cooling water filled inside the passive condensation cooling tank. By separately installing a plurality of cooling water circulation members inside the passive condensation cooling tank into which the steam generated by the steam generator flows in case the nuclear reactor malfunctions, the present invention is able to circulate the entire volume of the cooling water, not just part of the cooling water, filled inside the passive condensation cooling tank, thereby significantly improving the cooling efficiency of the cooling water flowing in from the steam generator.

Description

원자력 발전소의 피동이차응축시스템 {Passive Secondary Condensing System of An Atomic Power Plant} [0001] The present invention relates to a passive secondary condensing system of an atomic power plant,

본 발명은 원자력발전소의 피동이차응축시스템에 관한 것으로, 더욱 상세하게는 피동응축냉각탱크내부에 별도의 냉각수순환부재를 설치하여 피동응축냉각탱크내부에 차 있는 냉각수가 피동응축냉각탱크내부를 순환하도록 함으로써 증기발생기로부터 유입된 증기를 냉각시키는 냉각수의 냉각효율이 크게 향상될 수 있도록 하는 원자력발전소의 피동이차응축시스템에 관한 것이다.The present invention relates to a secondary secondary condensing system of a nuclear power plant, and more particularly, to a secondary secondary condensing system of a nuclear power plant, in which a separate cooling water circulating member is installed inside a passive condensing cooling tank, so that cooling water in the passive condensing cooling tank circulates in the driven condensing cooling tank So that the cooling efficiency of the cooling water for cooling the steam introduced from the steam generator can be greatly improved.

일반적으로 원자력발전소는 연료의 핵분열에 의해 생성된 열에너지를 이용하여 증기발생기를 통과하는 물에 열을 전달하여 증기를 발생시키고, 발생된 증기에 의해 터빈과 발전기를 가동시켜 전기에너지를 얻는 설비이다. Generally, a nuclear power plant uses heat energy generated by fission of fuel to transfer heat to water passing through a steam generator to generate steam, and the turbine and generator are operated by the generated steam to obtain electric energy.

원자력발전소는 핵연료를 보유하고 있는 원자로 노심과, 원자로에서 발생한 열에너지를 이차측으로 전달하는 원자로 냉각재 계통을 설계기준 범위 내에서 안전하게 운전되도록 함으로써 원자력발전소의 안전상태를 유지하고, 방사능 물질의 확산을 방지하기 위한 설비가 구비되어야 한다.Nuclear power plants maintain the safety status of nuclear power plants and prevent the spread of radioactive materials by ensuring that nuclear reactor core with nuclear fuel and reactor coolant system that transfers heat energy generated from nuclear reactor to secondary side are operated safely within the design standard range. .

이를 달성하기 위하여 원자력발전소는 사고 발생시 발전소를 안전하게 정지시킬 수 있도록 공학적 안전설비 계통을 갖추고 있다. 공학적 안전설비 계통은 격납용기계통(Containment System), 비상노심냉각계통(Emergency Core Cooling System), 피동보조급수계통(Passive Auxiliary Feedwater System)을 포함한다.To achieve this, the nuclear power plant has an engineering safety system to safely shut down the power plant in the event of an accident. Engineering safety systems include Containment System, Emergency Core Cooling System, and Passive Auxiliary Feedwater System.

공학적 안전설비계통중 종래의 피동보조급수계통에 대한 기술은 등록특허 10-1022164에 원자로의 열에 의해 증기를 발생시키는 증기발생기; 냉각수가 충진된 응축수조; 상기 응축수조 내에 위치하여, 상기 증기발생기에서 발생된 증기를 증기공급배관을 통해 공급받도록 설치되는 상부모관과, 상기 상부모관의 하부에 연결되는 열교환기와, 상기 열교환기의 하측 단부에 연결되어 응축수를 배출하는 하부모관; 상기 하부모관에 연결되어 상기 열교환기의 응축수를 상기 증기발생기로 공급하는 응축수회수배관을 포함하되, 상기 열교환기는, 경사진 두 직선구간과 상기 두 직선구간 사이를 연결하는 곡선 절곡구간으로 이루어진 U자형 부분이 하나 이상 형성된 튜브가 다수 개 병렬로 설치된 것으로 이루어지고, 상기 열교환기의 두 직선구간은 하향 경사지되, 지면과 이루는 예각이 3 내지 7도인 것으로 이루어지는 경수로의 피동 이차측 응축계통이 개시되어 있다.[0004] The conventional technology for the passive auxiliary water supply system of the engineering safety system includes a steam generator for generating steam by heat of the reactor in Patent Document 10-1022164; A condensate tank filled with cooling water; A condenser connected to a lower end of the heat exchanger and connected to a lower portion of the upper boiler pipe, and an upper boiler installed in the condenser tank to receive steam generated in the steam generator through a steam supply pipe; A lower core pipe for discharging; And a condensate return pipe connected to the lower boiler pipe and supplying condensed water of the heat exchanger to the steam generator, wherein the heat exchanger is a U-shaped boiler comprising a curved bending section connecting two inclined linear sections and the two linear sections, And the two straight sections of the heat exchanger are inclined downward and have an acute angle of 3 to 7 degrees with the ground surface, the secondary side condensation system of the light-water reactor is disclosed .

하지만 상기의 등록된 기술은 응축수조(피동응축냉각탱크)의 내부에 차 있는 냉각수중 응축기의 상측에 위치한 냉각수는 응축기로부터 열을 전달받아 자연대류가 일어나지만, 응축기의 하측에 차 있는 냉각수는 열을 공급받지 못해 자연대류가 일어나지 않음으로써 응축기의 상측에 위치한 냉각수와 섞이지 못하게 되어 응축수조(피동응축냉각탱크)로 유입되는 증기를 냉각시키는 냉각수의 냉각효율이 현저하게 떨어지는 문제점이 있었다.However, in the above-mentioned registered technology, the cooling water located in the upper part of the condenser among the cooling water inside the condensing water tank (passive condensation cooling tank) receives heat from the condenser and natural convection occurs. However, So that the cooling efficiency of the cooling water for cooling the steam flowing into the condensed water tank (the driven condensing cooling tank) is remarkably lowered because the natural convection does not occur and the water can not be mixed with the cooling water located on the upper side of the condenser.

본 발명은 상술한 바와 같은 문제점을 해결하기 위하여 안출 된 것으로, 피동응축냉각탱크내부에 별도의 냉각수순환부재를 설치하여 피동응축냉각탱크내부에 차 있는 냉각수가 피동응축냉각탱크내부를 순환하도록 함으로써 증기발생기로부터 유입된 증기를 냉각시키는 냉각수의 냉각효율이 크게 향상될 수 있도록 하는 원자력발전소의 피동이차응축시스템을 제공하는 데 그 목적이 있다.Disclosure of Invention Technical Problem [8] Accordingly, the present invention has been made keeping in mind the above problems occurring in the prior art, and an object of the present invention is to provide an apparatus and a method for cooling a passive condensation cooling tank, It is an object of the present invention to provide a passive secondary condensing system of a nuclear power plant capable of greatly improving cooling efficiency of cooling water for cooling steam flowing from a generator.

전술한 본 발명의 목적은, 증기발생기로부터 발생된 증기를 터빈측으로 이동시키는 주중기관으로부터 분기된 증기공급관; 상기 증기공급관에 연결되어 원자로의 오작동시 상기 증기공급관을 통해 증기를 공급받아 응축시키는 피동응축냉각탱크; 상기 피동응축탱크에 연결되어 상기 피동응축탱크로부터 응축된 냉각수를 주급수관에 공급하는 응축수회수관; 상기 응축수회수관에 연결되어 상기 피동응축탱크로부터 응축된 냉각수를 상기 응축수회수관으로부터 공급받아 증기발생기로 공급하는 주급수관;을 포함하되, 상기 피동응축냉각탱크는 내부에 상기 증기공급관으로부터 공급된 증기를 응축시키는 응축기와, 상기 피동응축냉각탱크의 내부에 차있는 냉각수를 순환시키는 냉각수순환부재가 구비된 것을 특징으로 하는 원자력 발전소의 피동이차응축시스템을 제공함으로써 달성된다.The above-described object of the present invention is achieved by a steam generator comprising: a steam supply pipe branched from a main engine for moving steam generated from a steam generator toward a turbine; A passive condensation cooling tank connected to the steam supply pipe to supply and condense steam through the steam supply pipe when a reactor malfunctions; A condensate return pipe connected to the passive condensation tank for supplying cooling water condensed from the passive condensation tank to the main water supply pipe; And a main water supply pipe connected to the condensate water recovery pipe and supplied with cooling water condensed from the passive condensation tank from the condensate water recovery pipe and supplying the condensed cooling water to the steam generator, And a cooling water circulating member for circulating the cooling water in the passive condensation cooling tank. The present invention also provides a passive secondary condensing system for a nuclear power plant.

본 발명의 경우 원자로의 오동작시 증기발생기로부터 생성된 증기가 유입되는 피동응축냉각탱크내부에 별도로 다수개의 냉각수순환부재를 설치함으로써 피동응축냉각탱크내부에 차 있는 냉각수 중 일부만이 순환하는 것이 아니라 냉각수 전체가 피동응축냉각탱크내부를 순환하도록 함으로써 증기발생기로부터 유입된 증기를 냉각시키는 냉각수의 냉각효율이 크게 향상되도록 하는 효과가 있다.In the case of the present invention, a plurality of cooling water circulation members are separately provided in the passive condensation cooling tank in which the steam generated from the steam generator flows when the reactor is malfunctioning, so that not only a part of the cooling water in the passive condensation cooling tank circulates, The cooling efficiency of the cooling water for cooling the steam introduced from the steam generator can be greatly improved by making the inside of the passive condensation cooling tank circulate.

또한 상기 냉각수순환부재는, 상기 피동응축냉각탱크의 내부에 설치된 응축기중 최하측에 위치한 응축기보다 하측에 위치하도록 설치되어, 상기 최하측에 위치한 응축기보다 하측에 위치한 냉각수가 상기 냉각수순환부재를 통해 상측에 위치한 냉각수와 섞이게 되는 것을 특징으로 한다.The cooling water circulation member is disposed below the condenser located at the lowermost one of the condensers provided in the passive condensation cooling tank so that the cooling water located below the condenser located at the lowermost side is communicated with the cooling water circulation member, Is mixed with the cooling water located in the < RTI ID = 0.0 >

상술한 바와 같은 본 발명인 원자력 발전소의 피동이차응축시스템은, 원자로의 오동작시 증기발생기로부터 생성된 증기가 유입되는 피동응축냉각탱크내부에 별도로 다수개의 냉각수순환부재를 설치함으로써 피동응축냉각탱크내부에 차 있는 냉각수중 일부만이 순환하는 것이 아니라 냉각수 전체가 피동응축냉각탱크내부를 순환하도록 함으로써 증기발생기로부터 유입된 증기를 냉각시키는 냉각수의 냉각효율이 크게 향상되도록 하는 효과가 있다.In the passive secondary condensing system of the nuclear power plant of the present invention, as described above, a plurality of cooling water circulation members are separately provided in the passive condensation cooling tank into which the steam generated from the steam generator flows when the reactor malfunctions, So that the cooling efficiency of the cooling water for cooling the steam introduced from the steam generator can be greatly improved by making the whole of the cooling water circulate in the passive condensation cooling tank.

도 1은 종래의 원자력발전소의 피동이차응축시스템의 구성도
도 2는 본 발명에 따른 원자력발전소의 피동이차응축시스템을 구성하는 피동응축탱크에 대한 투시도1 is a schematic view of a conventional secondary condensation system of a nuclear power plant
2 is a perspective view of a passive condensation tank constituting a driven secondary condensing system of a nuclear power plant according to the present invention;

이하 본 발명에 따른 일실시예를 첨부된 도면을 참조하여 상세하게 설명한다.Hereinafter, embodiments of the present invention will be described in detail with reference to the accompanying drawings.

도 1은 종래의 원자력발전소의 피동이차응축시스템의 구성도이고, 도 2는 본 발명에 따른 원자력발전소의 피동이차응축시스템을 구성하는 피동응축냉각탱크에 대한 투시도이다.2 is a perspective view of a passive condensation cooling tank constituting a driven secondary condensing system of a nuclear power plant according to the present invention. FIG. 1 is a schematic view of a conventional secondary condensing system of a nuclear power plant.

도 1에 나타난 바와 같이, 종래의 원자력발전소의 피동이차응축시스템은, 일반적인 가압경수로에 구비되는 구성으로서, 격납건물내에는 원자로를 순환하여 온도가 증가한 냉각수(미도시)와의 열교환에 의해 증기를 발생시키는 증기발생기(11)가 구비된다.As shown in FIG. 1, a conventional secondary condensation system of a nuclear power plant is provided in a general pressurized light water reactor. In the containment building, steam is generated by heat exchange with cooling water (not shown) A steam generator 11 is provided.

상기 증기발생기(11)의 상부에는 상기 증기발생기(11)에서 발생된 증기를 터빈(미도시)측으로 공급하는 주증기관(13)이 연결되고, 상기 증기발생기(11)의 하부에는 상기 증기발생기(11)로부터 공급된 증기가 상기 터빈을 통과하여 냉각수와의 열교환을 통해 물로 응축되고, 응축된 물이 증기발생기(11)로 회수되는 주급수관(19)이 연결된다.A steam generator 13 is connected to the upper portion of the steam generator 11 to supply the steam generated from the steam generator 11 to the turbine (not shown), and the steam generator 11 11 is condensed into water through heat exchange with the cooling water through the turbine, and the main water supply pipe 19 through which the condensed water is recovered to the steam generator 11 is connected.

상기 주증기관(13)에는 터빈측으로 증기발생기(11)에서 생성된 증기가 유입되는 것이 조절되도록 제1조절밸브(V1)가 설치되며, 원자로의 정상운전시에는 상기 제1조절밸브(V1)가 개방된 상태로 있게 되어 터빈측으로 증기가 공급되게 된다.The first control valve V1 is installed in the main combustion engine 13 so that the steam generated in the steam generator 11 is controlled to flow toward the turbine side and the first control valve V1 is opened And the steam is supplied to the turbine side.

또한 원자로의 오작동으로 인한 운전중단시에는 상기 제1조절밸브(V1)가 닫혀져 증기발생기(11)로부터 터빈측으로 증기가 공급되는 것이 차단되게 된다.In addition, when the operation of the reactor is interrupted due to a malfunction of the reactor, the first control valve V1 is closed and the supply of steam from the steam generator 11 to the turbine side is blocked.

상기 주급수관(19)에는 상기 터빈을 통과함으로써 응축된 물이 상기 주급수관(19)을 통해 증기발생기(11)로 회수되는 것이 조절되도록 제7조절밸브(V7)가 설치된다.The seventh control valve V7 is installed in the main water supply pipe 19 so that condensed water can be recovered to the steam generator 11 through the main water supply pipe 19 by passing through the turbine.

또한 상기 주급수관(19)에는 상기 피동응축냉각탱크(21)로부터 응축된 물이 상기 주급수관(19)에 유입되도록 응축수회수관(17)이 연결되며, 이때 상기 응축수회수관(17)의 일측은 상기 피동응축냉각탱크(21)에 연결되고 타측은 상기 주급수관(19)에 연결되어 응축된 물이 주급수관(19)으로 이동하게 된다.The condensed water recovery pipe 17 is connected to the main water pipe 19 so that condensed water from the passive condensation cooling tank 21 flows into the main water pipe 19. At this time, Is connected to the passive condensation cooling tank (21) and the other side is connected to the main water supply pipe (19) so that the condensed water moves to the main water supply pipe (19).

상기 응축수회수관(17)에는 응축된 물의 역류를 방지하기 위한 역류방지부(23)가 형성되고, 응축된 물이 상기 응축수회수관(17)으로의 유입을 조절하기 위한 제5조절밸브(V5)와 제6조절밸브(V6)가 상호 병렬로 연결된다.The condensate return pipe 17 is provided with a backflow prevention part 23 for preventing backflow of condensed water and a fifth control valve V5 for regulating the flow of condensed water into the condensate return pipe 17 And the sixth control valve V6 are connected in parallel with each other.

이외에 상기 주증기관(13)으로부터 분기되어 원자로의 오작동으로 인한 운전중단시 상기 증기발생기(11)로부터 발생된 증기가 상기 피동응축냉각탱크(21)에 유입되도록 증기공급관(15)이 형성된다.The steam supply pipe 15 is formed so that the steam generated from the steam generator 11 flows into the passive condensation cooling tank 21 when the operation is stopped due to the malfunction of the reactor.

상기 증기공급관(15)에는 상기 증기공급관(15)으로부터 상기 피동응축냉각탱크(21)로의 증기의 유입이 조절되도록 제2조절밸브)(V2)가 설치되고, 또한 증기 중에 포함된 수증기의 일부가 온도와 압력변화에 의해 응축될 경우 이를 배출하기 위한 제3조절밸브(V3)도 설치된다.The steam supply pipe 15 is provided with a second control valve V2 for controlling the inflow of steam from the steam supply pipe 15 to the passive condensation cooling tank 21 and a part of the steam contained in the steam A third control valve (V3) is also provided for discharging condensate when the temperature and pressure change.

상기 증기공급관(15)에는 상기 증기공급관(15)을 통해 유입된 증가가 물로 응축되도록 피동응축냉각탱크(21)가 연결되고, 이때 상기 피동응축냉각탱크(21)의 내부에는 상기 증기공급관(15)을 통해 유입된 증기를 냉각시키기 위한 냉각수(21b)가 차 있으며, 상기 증기발생기(11)로부터 유입된 증기와 냉각수(21b)사이에 열교환이 이루어지도록 응축기(21a)가 다수개 구비된다.The passive condensation cooling tank 21 is connected to the steam supply pipe 15 so that the increase introduced through the steam supply pipe 15 is condensed into water. In the passive condensation cooling tank 21, the steam supply pipe 15 A plurality of condensers 21a are provided so that heat is exchanged between the steam introduced from the steam generator 11 and the cooling water 21b.

또한 상기 응축기(21a)의 일측에는 비응축성 기체를 피동응축냉각탱크(21)로부터 배출하기 위한 제4조절밸브(V4)가 구비된다.A fourth control valve (V4) is provided at one side of the condenser (21a) for discharging non-condensable gas from the driven condensing cooling tank (21).

이에 더하여 상기 피동응축냉각탱크(21)의 하부에는 상기 피동응축냉각탱크(21)의 내부에 차있는 냉각수(21b)가 상하로 완전하게 순환하여 섞이도록 냉각수순환부재(21c)가 하나 이상 구비된다.In addition, at least one cooling water circulating member 21c is provided in the lower portion of the passive condensation cooling tank 21 so that the cooling water 21b stored in the passive condensation cooling tank 21 is completely circulated up and down .

따라서 상기 증기발생기(11)로부터 증기가 피동응축냉각탱크(21)에 공급되게 되면 증기가 상기 피동응축냉각탱크(21)의 내부에 구비된 응축기(21a)를 경유하면서 상기 피동응축냉각탱크(21)의 내부에 차 있는 냉각수(21b)에 의해 열을 빼앗겨 물로 응축되게 될 때, 상기 피동응축냉각탱크(21)의 내부에 구비된 응축기(21a)중 최하측에 위치한 응축기(21a)보다 하측에 차 있는 냉각수(21b)는 열을 흡수하지 못하여 상측으로 순환하지 못하게 되지만, 피동응축냉각탱크(21)내부의 최하측에 위치한 응축기(21a)보다 하측에 위치하도록 냉각수순환부재(21c)를 구비시킴으로써, 열을 흡수하지 못하여 순환되지 못하는 냉각수(21b)도 응축기(21a)로부터 열을 흡수하여 순환하는 상측에 위치한 냉각수(21b)와 순환되어 섞이도록 함으로써 냉각수(21b)전체가 피동응축냉각탱크(21)내부를 순환하도록 하여 냉각수(21b)전체가 유입된 증기로부터 열을 흡수할 수 있도록 한다.Therefore, when the steam is supplied from the steam generator 11 to the driven condensing cooling tank 21, the steam is supplied to the passive condensation cooling tank 21 via the condenser 21a provided in the passive condensing cooling tank 21 (21a) provided in the inside of the passive condensation cooling tank (21), when the heat is absorbed by the cooling water (21b) inside the condenser (21a) The cooling water 21b can not absorb heat and can not circulate upward. By providing the cooling water circulation member 21c so as to be positioned below the lowermost condenser 21a inside the passive condensation cooling tank 21 And the cooling water 21b which can not be circulated due to the heat absorption can be circulated and mixed with the cooling water 21b located on the upper side by absorbing heat from the condenser 21a to circulate the cooling water 21b to the passive cooling cooling tank 21 )of mine So that the entire cooling water 21b can absorb heat from the steam into which it is introduced.

따라서 피동응축냉각탱크(21)에 차있는 냉각수(21b) 중 일정량만이 증기로부터 열을 흡수하는 것이 아니라 냉각수(21b) 전체가 열 흡수 기능을 수행할 수 있도록 하여 증기를 냉각시키는 냉각수(21b)의 냉각효율을 크게 향상시킬 수 있게 된다. Therefore, not only a certain amount of the cooling water 21b in the passive condensation cooling tank 21 absorbs heat from the steam but also the cooling water 21b, which cools the steam by allowing the entire cooling water 21b to perform the heat absorbing function, It is possible to greatly improve the cooling efficiency.

이하 상기와 같은 구성을 가진 원자력 발전소의 피동이차응축시스템의 동작과정에 대해 상세히 설명한다.Hereinafter, the operation of the passive secondary condensing system of the nuclear power plant having the above-described configuration will be described in detail.

먼저 격납건물내에는 원자로를 통과하여 온도가 상승한 냉각수(미도시)에 의해 증기를 발생시키는 증기발생기(11)가 구비된다.First, a steam generator 11 for generating steam by cooling water (not shown) having a temperature rising through a reactor is provided in a containment building.

상기 증기발생기(11)를 통해 생성된 증기는 상기 주증기관(13)을 통해 터빈(미도시)측으로 공급되게 되고, 상기 터빈은 공급된 증기를 통해 가동되게 된다.The steam generated through the steam generator 11 is supplied to the turbine (not shown) through the main steam generator 13, and the steam turbine is operated through the supplied steam.

이때 오작동으로 인해 원자로의 운전이 중단되게 되면, 상기 주증기관(13)으로 유입되는 증기가 제1조절밸브(V1)를 통해 차단되게 되고, 상기 증기발생기(11)를 통해 생성된 증기는 상기 주증기관(13)으로부터 분기된 증기공급관(15)으로 유입되어 상기 제2조절밸브(V2)가 개방되면서 증기공급관(15)에 연결된 피동응축냉각탱크(21)에 공급되게 된다.At this time, when the operation of the reactor is stopped due to a malfunction, the steam flowing into the main steam pipe 13 is blocked through the first control valve V1, and the steam generated through the steam generator 11 is steamed Is introduced into the steam supply pipe 15 branched from the engine 13 and supplied to the passive condensation cooling tank 21 connected to the steam supply pipe 15 while the second control valve V2 is opened.

이후 피동응축냉각탱크(21)에 공급된 증기는 피동응축냉각탱크(21)의 내부에 구비된 다수개의 응축기(21a)를 경유하게 되며 이때 피동응축냉각탱크(21)의 내부에 차 있는 냉각수(21b)에 의해 열을 빼앗기면서 응축되어 물(냉각수)이 생성되게 된다.Thereafter, the steam supplied to the passive condensation cooling tank 21 passes through a plurality of condensers 21a provided in the passive condensation cooling tank 21. At this time, the cooling water in the passive condensation cooling tank 21 21b to condense while generating heat (cooling water).

이때 증기가 피동응축냉각탱크(21)의 내부에 구비된 응축기(21a)를 경유할 때 냉각수(21b)가 증기로부터 열을 흡수하는 경우 응축기(21a)의 상측에 위치한 냉각수(21b)는 열을 흡수하여 자연대류에 의해 상측으로 상승하면서 순환하게 되지만, 응축기(21a)의 하측에 위치한 냉각수(21b)는 증기로부터 열을 흡수하지 못하여 상측에 위치한 냉각수(21b)와 순환하지 못하게 된다.At this time, when the cooling water 21b absorbs heat from the steam when the steam passes through the condenser 21a provided in the passive condensation cooling tank 21, the cooling water 21b located above the condenser 21a generates heat The cooling water 21b located below the condenser 21a can not absorb heat from the steam and can not circulate with the cooling water 21b located on the upper side.

따라서 본 발명의 경우 상기 피동응축냉각탱크(21)의 내부에 구비된 응축기(21a)중 최하측에 위치한 응축기(21a)보다 하측에 냉각수순환부재(21c)를 다수개 설치하여 상측에 위치한 냉각수(21b)와 순환되도록 함으로써 피동응축냉각탱크(21)에 내부에 차 있는 냉각수(21b) 전체가 증기발생기(11)로부터 유입된 증기를 냉각시키는데 작용하도록 하여 증기를 냉각시키는 냉각수(21b)의 냉각효율이 커지게 하는 효과가 있게 된다.Therefore, in the present invention, a plurality of cooling water circulation members 21c are provided below the condenser 21a located at the lowermost one of the condensers 21a provided in the passive condensation cooling tank 21, The entire cooling water 21b stored in the passive condensation cooling tank 21 functions to cool the steam introduced from the steam generator 11 so that the cooling efficiency of the cooling water 21b cooling the steam Is increased.

이후 상기 피동응축냉각탱크(21)내부에서 응축된 물은 자체하중에 의해 아래로 낙하되어 응축수회수관(17)을 거쳐 주급수관(19)에 공급되게 되고 주급수관(19)에 공급된 물(냉각수)은 주급수관(19)을 통해 증기발생기(11)로 공급되어 오작동중인 원자로를 냉각시키게 된다.
The condensed water in the passive condensation cooling tank 21 is then dropped down by its own load and supplied to the main water supply pipe 19 through the condensed water recovery pipe 17 and the water supplied to the main water supply pipe 19 Cooling water) is supplied to the steam generator 11 through the main water supply pipe 19 to cool the malfunctioning reactor.

상기에서 설명한 바와 같이 본 발명의 경우 증기발생기(11)로부터 유입된 증기를 물로 응축시키는 피동응축냉각탱크(21)의 내부에 다수개의 냉각수순환부재(21c)를 구비시켜 특정한 위치의 냉각수(21b)만이 순환하는 것이 아니라 냉각수(21b) 전체가 순환되도록 하여 냉각수(21b)전체가 흡열기능을 수행하도록 함으로써 증기로부터 열을 빼았는 냉각수(21b)의 냉각효율이 크게 향상되도록 하는 효과가 있게 된다.
As described above, in the present invention, a plurality of cooling water circulating members 21c are provided in the passive condensation cooling tank 21 for condensing the steam introduced from the steam generator 11 into water, so that the cooling water 21b at a specific position is provided. The whole of the cooling water 21b is circulated so that the entire cooling water 21b performs the heat absorbing function so that the cooling efficiency of the cooling water 21b from which the heat is removed from the steam can be greatly improved.

이상에서 본 발명의 바람직한 일실시예를 설명하였으나, 본 발명은 다양한 변화와 변경 및 균등물을 사용할 수 있고, 상기 실시예를 적절히 변형하여 동일하게 응용할 수 있음이 명확하다. 따라서 상기 기재내용은 하기 특허청구범위의 한계에 의해 정해지는 본 발명의 범위를 한정하는 것이 아니다.While the invention has been shown and described with reference to certain preferred embodiments thereof, it will be understood by those skilled in the art that various changes and modifications may be made therein without departing from the spirit and scope of the invention as defined by the appended claims. Therefore, the above description does not limit the scope of the present invention, which is defined by the limitations of the following claims.

11: 증기발생기 13: 주증기관
15: 증기공급관 17: 응축수회수관
19: 주급수관 21: 피동응축냉각탱크
21a: 응축기 21b: 냉각수
21c: 냉각수순환부재 23: 역류방지부재
V1: 제1조절밸브 V2: 제2조절밸브
V3: 제3조절밸브 V4: 제4조절밸브
V5: 제5조절밸브 V6: 제6조절밸브
V7: 제7조절밸브11: Steam generator 13:
15: steam supply pipe 17: condensate return pipe
19: Main water pipe 21: Passive condensation cooling tank
21a: condenser 21b: cooling water
21c: cooling water circulation member 23: backflow prevention member
V1: first control valve V2: second control valve
V3: third control valve V4: fourth control valve
V5: fifth control valve V6: sixth control valve
V7: Seventh control valve

Claims (2)

증기발생기로부터 발생된 증기를 터빈측으로 이동시키는 주중기관으로부터 분기된 증기공급관;
상기 증기공급관에 연결되어 원자로의 오작동시 상기 증기공급관을 통해 증기를 공급받아 응축시키는 피동응축냉각탱크;
상기 피동응축탱크에 연결되어 상기 피동응축탱크로부터 응축된 냉각수를 주급수관에 공급하는 응축수회수관;
상기 응축수회수관에 연결되어 상기 피동응축탱크로부터 응축된 냉각수를 상기 응축수회수관으로부터 공급받아 증기발생기로 공급하는 주급수관;을 포함하되,
상기 피동응축냉각탱크는,
내부에 상기 증기공급관으로부터 공급된 증기를 응축시키는 응축기와, 상기 피동응축냉각탱크의 내부에 차있는 냉각수를 순환시키는 냉각수순환부재가 구비된 것을 특징으로 하는 원자력 발전소의 피동이차응축시스템.
A steam supply pipe branched from a main engine for moving the steam generated from the steam generator toward the turbine side;
A passive condensation cooling tank connected to the steam supply pipe to supply and condense steam through the steam supply pipe when a reactor malfunctions;
A condensate return pipe connected to the passive condensation tank for supplying cooling water condensed from the passive condensation tank to the main water supply pipe;
And a main water supply pipe connected to the condensate water recovery pipe to supply cooling water condensed from the passive condensation tank from the condensate water recovery pipe to the steam generator,
The passive condensation cooling tank includes:
A condenser for condensing the steam supplied from the steam supply pipe and a cooling water circulating member for circulating the cooling water in the passive condensation cooling tank.
제1항에 있어서,
상기 냉각수순환부재는,
상기 피동응축냉각탱크의 내부에 설치된 응축기중 최하측에 위치한 응축기보다 하측에 위치하도록 설치되어,
상기 최하측에 위치한 응축기보다 하측에 위치한 냉각수가 상기 냉각수순환부재를 통해 상측에 위치한 냉각수와 섞이게 되는 것을 특징으로 하는 원자력 발전소의 피동이차응축시스템.

The method according to claim 1,
The cooling water circulating member
And a condenser disposed in a lower side of a condenser located in the lowermost one of the condensers provided in the passive condensation cooling tank,
Wherein the cooling water located below the lowermost condenser is mixed with the cooling water located on the upper side through the cooling water circulation member.

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JP2006138744A (en) 2004-11-12 2006-06-01 Mitsubishi Heavy Ind Ltd Reactor cooling device
KR101160771B1 (en) * 2011-01-03 2012-06-28 한국수력원자력 주식회사 Condensation-tank optimization of advanced passive auxiliary feed-water system for pressurized water reactor

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* Cited by examiner, † Cited by third party
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