KR20130131757A - Passive safety injection system using vapor drive pump - Google Patents

Passive safety injection system using vapor drive pump Download PDF

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KR20130131757A
KR20130131757A KR1020120055546A KR20120055546A KR20130131757A KR 20130131757 A KR20130131757 A KR 20130131757A KR 1020120055546 A KR1020120055546 A KR 1020120055546A KR 20120055546 A KR20120055546 A KR 20120055546A KR 20130131757 A KR20130131757 A KR 20130131757A
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South Korea
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steam
pressurizer
turbine
pressure vessel
pipe
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KR1020120055546A
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Korean (ko)
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김경두
정법동
황문규
이승준
이승욱
김병재
배성원
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한국원자력연구원
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Priority to KR1020120055546A priority Critical patent/KR20130131757A/en
Publication of KR20130131757A publication Critical patent/KR20130131757A/en

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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
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/086—Pressurised water reactors
    • 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
    • G21C15/243—Promoting flow of the coolant for liquids
    • 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)
  • Jet Pumps And Other Pumps (AREA)

Abstract

The present invention relates to a steam driven pump and the passive safety injection system thereof, and more particularly, to a pressure-reactor pressure vessel of which one end is connected to the other end of the reload transfer from the storage tank inside the pressure-fed of the reactor pressure vessel to circulate the transmission cycle installed in the pipe conduit, comprises a valve of which the entire AC power loss of the DC power supply is possible during the circulation by lowering the pressure inside the pipe to reload the transmission generated from the pressurizer steam distribution pipes and connections, a plumbing pipe connected to the pressurizer, a pusher connected to the other end of the opening and closing valve of the connecting pipe is opened when the steam supply received by the turbine to produce power, and the power from the turbine of the steam driven pump and a supply operation are received, a vapor pump activated when the drive accommodated inside the water is pressure-fed into the reactor pressure vessel inside the injection tank, thus unexpected accident caused from the entire primary system in case the power is cut off to drop the flow pressure of the temperature inside the reactor pressure vessel can be decreased and effective.

Description

증기구동펌프를 이용한 피동안전주입계통{Passive Safety Injection System using Vapor Drive Pump}Passive Safety Injection System using Vapor Drive Pump

본 발명은 증기구동펌프를 이용한 피동안전주입계통에 관한 것으로서, 특히 비상상황이 발생되어 원자력발전설비 1차계통의 전체교류전원이 차단되었을 때 가압형원자로 압력용기 내부의 온도를 낮출 수 있는 증기구동펌프를 이용한 피동안전주입계통에 관한 것이다.
The present invention relates to a pneumatic injection system using a steam driving pump, and particularly, a steam driving system capable of lowering the temperature inside a pressure vessel as a pressurized reactor when an emergency occurs and the entire AC power supply to the nuclear power plant is cut off. The present invention relates to a pre-injection system using a pump.

일반적인 가압경수형 원자력발전설비의 1차계통은 노심을 냉각시키기 위하여 재장전수 저장탱크로부터 붕소가 함유된 재장전수를 공급받는 가압형원자로 압력용기와, 일단이 타단이 상기 가압형원자로 압력용기의 연통되는 순환배관과, 상기 순환배관의 관로상에 설치되는 가압기와 증기발생기 및 원자로냉각재펌프를 포함하여 구성된다.In general, the primary system of pressurized water-type nuclear power plant is a pressurized reactor receiving boron-containing reloading water from a reloading storage tank to cool the core, and the other end of the pressurized reactor is in communication with the pressurized reactor. And a pressurizer, a steam generator, and a reactor coolant pump installed on the circulating pipe and the circulating pipe.

이렇게 구성되는 원자력발전설비의 1차계통에 비상상황이 발생되어 전체교류전원이 상실되면 가압기와 증기발생기 및 원자로냉각재펌프 등의 작동이 정지되어 가압형원자로 압력용기에 냉각수가 공급되지 않아서 가압형원자로 압력용기 내부의 온도의 상승을 제어하지 못하는 문제점이 있었다.
If an emergency occurs in the primary system of the nuclear power plant thus constructed, and the total AC power is lost, the pressurizer, steam generator, and reactor coolant pump are stopped, and no cooling water is supplied to the pressure vessel. There was a problem in that the temperature rise inside the pressure vessel could not be controlled.

본 발명은 상기한 종래기술의 문제점을 해결하기 위하여 안출된 것으로서, 비상상황이 발생되어 원자력발전설비 1차계통의 전체교류전원이 차단되었을 때 1차계통의 순환배관 내부에 존재하는 재장전수로부터 발생된 증기의 힘으로 터빈을 돌려 전력을 생산한 후 이 전력으로 증기구동펌프를 작동시켜 냉각수를 가압형원자로 압력용기에 투입할 수 있는 증기구동펌프를 이용한 피동안전주입계통을 제공하는데 그 목적이 있다.
The present invention has been made to solve the above problems of the prior art, when an emergency situation occurs from the reloading water present in the circulation pipe of the primary system when the total AC power of the nuclear power plant primary system is cut off. The purpose is to provide a pre-injection system using a steam driven pump that can supply cooling water to a pressure vessel by operating a steam driven pump using the power generated by turning a turbine with the power of steam. .

상기한 과제를 해결하기 위한 본 발명에 의한 증기구동펌프를 이용한 피동안전주입계통은 가압형원자로 압력용기에 일단과 타단이 연결되어 재장전수 저장탱크로부터 상기 가압형원자로 압력용기 내부로 공급된 재장전수를 순환시키는 순환배관의 관로상에 설치되는 가압기에 일단이 연결되어, 전체교류전원 상실시 상기 순환배관 내부의 압력 하강에 의하여 재장전수로부터 발생된 증기를 유통시키는 가압기 연결배관과; 상기 가압기 연결배관의 관로상에 설치되어 전체교류전원 상실시 직류전원에 의하여 개방되는 개폐밸브와; 상기 가압기 연결배관의 타단에 연결되어 상기 개폐밸브가 개방되었을 때 공급받은 증기에 의해 전력을 생산하는 터빈과; 상기 터빈으로부터 전력을 공급받아 작동하는 증기구동펌프와; 상기 증기구동펌프가 작동될 때 내부에 수용된 물이 상기 가압형원자로 압력용기 내부로 투입되는 인젝션탱크;를 포함하여 구성된다.Recharged water supply system using the steam driving pump according to the present invention for solving the above problems is connected to one end and the other end of the pressure vessel to the pressure vessel, the reloading water supplied into the pressure vessel from the reloading water storage tank A pressurizer connecting pipe having one end connected to a pressurizer installed on a circulating pipe for circulating the circulating pipe and distributing steam generated from the reloaded water due to the pressure drop inside the circulation pipe; An opening / closing valve installed on a pipe of the pressurizer connecting pipe and opened by a DC power supply; A turbine connected to the other end of the pressurizer connecting pipe to produce electric power by steam supplied when the on / off valve is opened; A steam driving pump operated by receiving electric power from the turbine; It is configured to include; an injection tank into which the water contained therein is introduced into the pressure vessel as the pressurized reactor when the steam driving pump is operated.

여기서, 상기 가압기 연결배관을 통하여 터빈으로 공급되어 터빈의 전력생산에 이용된 후 액체로 상변화된 증기는 상기 재장전수 저장탱크로 유입된다.Here, the steam which is supplied to the turbine through the pressurizer connecting pipe and used for power generation of the turbine is changed into liquid and flows into the reloading water storage tank.

그리고, 전체교류전원 상실시 상기 증기구동펌프는 상기 재장전수 저장탱크로부터 재장전수를 끌어들여 상기 가압형원자로 압력용기 내부로 투입한다.In addition, the steam driving pump at all the alternating current power supply draws the reloaded water from the reloaded water storage tank and enters the pressurized reactor into the pressure vessel.

또한, 상기 개폐밸브와 터빈 사이의 가압기 연결배관 관로상에는 습분분리기가 더 설치된다.
In addition, a moisture separator is further installed on the pressurizer connecting pipe line between the on-off valve and the turbine.

상기와 같이 구성되는 본 발명의 증기구동펌프를 이용한 피동안전주입계통은 종래의 원자력발전설비 1차계통의 가압기에 가압기 연결배관을 설치하고, 이 가압기 연결배관을 통하여 공급되는 증기로 터빈을 돌려 전력을 생산한 후, 그 전력으로 증기구동펌프를 작동시켜 인젝션탱크의 냉각수와 재장전수 저장탱크의 재장전수를 가압형원자로 압력용기 내부에 투입하므로, 예상치 못한 사고로 1차계통의 전체교류전원이 차단되어도 가압형원자로 압력용기 내부의 온도를 강하(降下)시킬 수 있어서 안전주입계통의 신뢰도를 향상시킬 수 있는 이점이 있다.The blood injection system using the steam driving pump of the present invention constituted as described above is provided with a pressurizer connecting pipe in a pressurizer of a conventional nuclear power plant primary system, and turns a turbine into steam supplied through the pressurizer connecting pipe. After the production, the steam driving pump is operated with the power to cool the injection tank and the reloading water of the reloading water storage tank into the pressurized reactor inside the pressure vessel, which shuts down the entire AC power supply in the primary system due to an unexpected accident. Even if it is a pressurized reactor, the temperature inside the pressure vessel can be lowered, thereby improving the reliability of the safety injection system.

또한, 가압기 연결배관을 통하여 공급되어 터빈을 돌리고 난 후 액체로 상변화된 증기를 재장전수 저장탱크로 이송시키고, 재장전수 저장탱크 내부에 수용된 물을 증기구동펌프가 가압형원자로 압력용기 내부로 투입하므로, 터빈을 가동시킨 증기를 재활용할 수 있는 이점이 있다.
In addition, after the turbine is supplied through the connecting pipe of the pressurizer and the turbine is rotated, the vapor, which is changed into liquid, is transferred to the reloading water storage tank. In addition, there is an advantage that can recycle the steam to operate the turbine.

도 1은 본 발명에 의한 증기구동펌프를 이용한 피동안전주입계통의 계통도.1 is a system diagram of a blood injection system using a steam drive pump according to the present invention.

이하, 본 발명에 의한 증기구동펌프를 이용한 피동안전주입계통의 실시 예를 첨부된 도면을 참조하여 상세히 설명한다.Hereinafter, with reference to the accompanying drawings, an embodiment of a blood injection system using a steam drive pump according to the present invention will be described in detail.

도 1은 본 발명에 의한 증기구동펌프를 이용한 피동안전주입계통의 계통도이다.
1 is a schematic diagram of a blood injection system using a steam driving pump according to the present invention.

본 발명에 의한 증기구동펌프를 이용한 피동안전주입계통은 1차계통의 원자력발전설비에 연결되는 것으로서, 1차계통의 가압기(40)에 연결되는 가압기 연결배관(100)과, 상기 가압기 연결배관(100)의 관로상에 설치되는 개폐밸브(200)와, 상기 가압기 연결배관(100)에 연결되는 터빈(300)과, 상기 터빈(300)과 전기적으로 연결된 증기구동펌프(400)와, 상기 증기구동펌프(400)와 연결되는 인젝션탱크(500)와, 상기 가압기 연결배관(100)의 관로상에 설치되는 습분분리기(MSR:Moisture Separator Reheater,600)를 포함하여 구성된다.
The blood injection system using the steam driving pump according to the present invention is connected to the nuclear power plant of the primary system, the pressurizer connecting pipe 100 connected to the pressurizer 40 of the primary system, and the pressurizer connecting pipe ( On-off valve 200 is installed on the pipeline of the 100, the turbine 300 is connected to the pressurizer connecting pipe 100, the steam drive pump 400 electrically connected to the turbine 300, and the steam An injection tank 500 connected to the driving pump 400 and a moisture separator (MSR) 600 installed on a conduit of the pressurizer connecting pipe 100 are configured.

상기 가압기 연결배관(100)은 일단이 상기 가압기(40)에 연결되어 전체교류전원 상실시 상기 순환배관(30) 내부에 압력 하강에 의하여 재장전수로부터 발생된 증기를 유통시킨다. The pressurizer connecting pipe 100 has one end connected to the pressurizer 40 so as to distribute steam generated from the reloading water due to the pressure drop inside the circulation pipe 30.

좀 더 자세히 설명하면, 일반적인 원자력발전설비의 1차계통은 붕소가 함유된 재장전수를 수용하는 재장전수 저장탱크(RWST:Refueling Water Storage Tank,10)와, 노심을 냉각시키기 위하여 상기 재장전수 저장탱크(10)로부터 재장전수를 공급받는 가압형원자로 압력용기(20)와, 일단이 상기 가압형원자로 압력용기(20)의 일측에 연통되고 타단이 상기 가압형원자로 압력용기(20)의 타측에 연통되어 재장전수 저장탱크(10)로부터 상기 가압형원자로 압력용기(20) 내부에 공급된 재장전수를 순환시키는 순환배관(30)과, 상기 순환배관(30)의 관로상에 설치되는 가압기(PZR:Pressurizer,40)와, 상기 순환배관(30)의 관로상에 설치되는 증기발생기(50)와, 상기 순환배관(30)의 관로상에 설치되는 원자로냉각재펌프(60)를 포함하여 구성된다.In more detail, the primary system of a general nuclear power plant includes a refueling water storage tank (RWST) 10 containing boron-containing reloading water, and the reloading water storage tank for cooling the core. Pressurized reactor 20 receives the reloading water from the pressure vessel 20, one end is in communication with one side of the pressure vessel 20, the other end is in communication with the other side of the pressure vessel 20 the pressure-type reactor. A recirculation pipe 30 for circulating the reloading water supplied from the reloading water storage tank 10 to the pressurized reactor 20 inside the pressure vessel 20, and a pressurizer (PZR) installed on a conduit of the circulation pipe 30: Pressurizer 40, the steam generator 50 is installed on the duct of the circulation pipe 30, and the reactor coolant pump 60 is provided on the duct of the circulation pipe 30.

상기와 같은 일반적인 원자력발전설비의 1차계통 중에서 가압기(40)는 높은 압력을 가하여 순환배관(30) 내부의 재장전수가 고온이 되어도 증기가 되지 않고 액체상태를 유지하도록 한다. 이러한 기능을 갖는 가압기(40)에 가압기 연결배관(100)의 일단이 연결되는 것이다. 이렇게 가압기(40)에 가압기 연결배관(100)이 연결된 상태에서 원자력발전설비 1차계통의 전체교류전원이 상실되면 가압기(40)의 작동이 중단되고, 가압기(40)의 작동이 중단되면 순환배관(30) 내부에 고압을 가할 수가 없어서 순환배관(30) 내부의 압력이 하강된다. 연이어 순환배관(30) 내부의 압력이 하강되면 상대적으로 낮은 온도에서 액체가 끓기 때문에 순환배관(30) 내부에 존재하는 재장전수가 끓어 재장전수로부터 증기가 발생된다. 이렇게 순환배관(30) 내부에서 재장전수가 끓어 발생된 증기는 가압기(40) 내부를 통과하여 가압기 연결배관(100) 내부로 유입된다.
In the primary system of the general nuclear power plant as described above, the pressurizer 40 is applied with a high pressure to maintain a liquid state without becoming steam even when the reloading water inside the circulation pipe 30 becomes hot. One end of the pressurizer connecting pipe 100 is connected to the pressurizer 40 having such a function. When the total alternating power of the nuclear power plant primary system is lost in the state in which the pressurizer connection pipe 100 is connected to the pressurizer 40, the operation of the pressurizer 40 is stopped, and the operation of the pressurizer 40 stops the circulation pipe. (30) It is not possible to apply a high pressure inside the pressure inside the circulation pipe 30 is lowered. Subsequently, when the pressure inside the circulation pipe 30 drops, the liquid is boiled at a relatively low temperature, so that the reloading water present in the circulation pipe 30 boils and steam is generated from the reloading water. The steam generated by the reloading water boils in the circulation pipe 30 and passes through the pressurizer 40 to be introduced into the pressurizer connecting pipe 100.

상기 개폐밸브(200)는 상기 가압기 연결배관(100)의 관로상에 설치되어 전체교류전원 상실시에 공급되는 직류전원(DC전원)에 의하여 개방된다. 이 개폐밸브(200)는 상기 가압기(40)에 인접한 가압기 연결배관(100)의 관로상에 설치되어 평상시에는 폐쇄상태를 유지한다. 평상시 폐쇄상태를 유지함으로써 가압기(40)에서 가하는 압력이 가압기 연결배관(100) 상으로 누설되지 않도록 하여 온전한 압력이 순환배관(30)에 제공되는 것이다. 그러다가 비상사태가 발생하여 원자력발전설비 1차계통의 전체교류전원이 상실되면 개폐밸브(200)에 직류전원이 공급되어 개폐밸브(200)가 개방되고, 개폐밸브(200)가 개방되면 순환배관(30) 내부의 재장전수에서 발생된 증기가 가압기(40)를 거쳐서 가압기 연결배관(100) 내부로 유입되는 것이다.
The on-off valve 200 is installed on the line of the pressurizer connecting pipe 100 and is opened by a DC power supply (DC power) supplied at the time of the entire AC power supply. The on-off valve 200 is installed on the conduit of the pressurizer connecting pipe 100 adjacent to the pressurizer 40 to maintain a closed state in normal times. By maintaining the normally closed state, the pressure applied from the pressurizer 40 is prevented from leaking onto the pressurizer connecting pipe 100 so that intact pressure is provided to the circulation pipe 30. Then, when an emergency occurs and the total AC power of the nuclear power plant primary system is lost, DC power is supplied to the shut-off valve 200 to open and close the valve 200, and when the shut-off valve 200 is opened, the circulation pipe ( 30) The steam generated from the reloading water is introduced into the pressurizer connecting pipe 100 through the pressurizer 40.

상기 터빈(300)은 상기 가압기 연결배관(100)의 타단에 연결되어 상기 개폐밸브(200)가 개방되었을 때 공급받은 증기에 의해 전력을 생산한다. 앞서 말한대로 전체교류전원이 상실되면 개폐밸브(200)가 개방되고 상기 가압기 연결배관(100) 내부에 유입된 증기는 터빈(300)까지 전달되어, 이 증기가 터빈(300)을 돌려서 전력이 생산된다.The turbine 300 is connected to the other end of the pressurizer connecting pipe 100 to produce electric power by the steam supplied when the on-off valve 200 is opened. As described above, when the total AC power is lost, the on-off valve 200 is opened and steam introduced into the pressurizer connecting pipe 100 is transferred to the turbine 300, and the steam rotates the turbine 300 to produce power. do.

그리고, 상기 가압기 연결배관(100)을 통하여 터빈(300)으로 공급되어 터빈(300)의 전력생산에 이용된 후 액체로 상변화된 증기는 상기 재장전수 저장탱크(10)로 유입된다. 즉, 상기 가압기 연결배관(100)을 통하여 공급된 증기가 터빈(300)을 돌리고 난 이후에는 액체로 상변화가 되는데, 이 액체로 상변화된 증기는 상기 터빈(300)과 재장전수 저장탱크(10) 사이에 연결된 제1이송배관(P1)을 통하여 재장전수 저장탱크(10)로 안내된다.
Then, the steam supplied to the turbine 300 through the pressurizer connecting pipe 100 and used for power generation of the turbine 300 is changed into a liquid and flows into the reloading water storage tank 10. That is, after the steam supplied through the pressurizer connecting pipe 100 turns the turbine 300, the phase changes to liquid. The vapor phase changed into the liquid is the turbine 300 and the reload water storage tank 10. It is guided to the reloading water storage tank 10 through the first transfer pipe (P1) connected between.

상기 증기구동펌프(400)는 상기 터빈(300)으로부터 전력을 공급받아 작동한다. 즉, 전체교류전원이 상실되면 가압기 연결배관(100)을 따라 터빈(300) 쪽으로 증기가 이동되어 이 증기가 터빈(300)을 돌려 전력이 생산되며, 이렇게 생산된 전력을 증기구동펌프(400)가 제공받아 작동된다.
The steam driving pump 400 operates by receiving power from the turbine 300. That is, when the total AC power is lost, the steam is moved toward the turbine 300 along the pressurizer connecting pipe 100, and the steam rotates the turbine 300 to produce power, and the generated power is driven by the steam driving pump 400. Is provided and operated.

상기 인젝션탱크(500)는 내부에 물, 즉 냉각수가 수용된다. 이러한 인젝션탱크(500)는 상기 증기구동펌프(400)와 제2이송배관(P2)에 의하여 연결된다. 따라서, 전체교류전원이 상실되어 상기 증기구동펌프(400)가 작동될 때 인젝션탱크(500) 내부에 수용된 냉각수는 상기 제2이송배관(P2)을 통하여 증기구동펌프(400) 쪽으로 안내된다.
The injection tank 500 accommodates water, that is, cooling water. The injection tank 500 is connected by the steam drive pump 400 and the second transfer pipe (P2). Therefore, when the total AC power is lost and the steam driving pump 400 is operated, the coolant contained in the injection tank 500 is guided toward the steam driving pump 400 through the second transfer pipe P2.

한편, 상기 증기구동펌프(400)는 상기 가압형원자로 압력용기(20)와 제3이송배관(P3)을 통하여 연결된다. 이렇게 상기 증기구동펌프(400)가 제2이송배관(P2)에 의하여 인젝션탱크(500)와 연결되고 제3이송배관(P3)에 의하여 가압형원자로 압력용기(20)와 연결되기 때문에 증기구동펌프(400)가 작동되었을 때 증기구동펌프(400)는 인젝션탱크(500) 내부에 수용된 물을 제2이송배관(P2)을 통하여 끌어들인 후 제2이송배관(P2)을 통하여 상기 가압형원자로 압력용기(20) 내부로 투입한다. 따라서, 원자력발전설비 1차계통의 전체교류전원이 차단된다 하더라도 냉각수가 가압형원자로 압력용기(20) 내부로 투입되어 상기 가압형원자로 압력용기(20) 내부의 온도가 상승되는 것을 방지할 수 있다.
On the other hand, the steam drive pump 400 is connected to the pressurized reactor through the pressure vessel 20 and the third transfer pipe (P3). Since the steam drive pump 400 is connected to the injection tank 500 by the second transfer pipe (P2) and is connected to the pressure vessel (20) by the pressurized reactor by the third transfer pipe (P3) steam drive pump. When 400 is operated, the steam driving pump 400 draws water contained in the injection tank 500 through the second feed pipe P2 and then pressurizes the pressurized reactor through the second feed pipe P2. It is put into the container 20. Therefore, even if the total AC power of the nuclear power plant primary system is cut off, the coolant is introduced into the pressure vessel 20 into the pressurized reactor to prevent the temperature inside the pressurized reactor 20 from rising. .

또한, 상기 증기구동펌프(400)는 상기 재장전수 저장탱크(10)와 제4이송배관(P4)에 의하여 연결된다. 따라서, 전체교류전원 상실시에 상기 증기구동펌프(400)는 전체교류전원 상실시 상기 인젝션탱크(500)로부터 냉각수를 공급받아 가압형원자로 압력용기(20) 내부에 투입하고, 동시에 상기 재장전수 저장탱크(10)로부터 재장전수를 끌어들여 가압형원자로 압력용기(20) 내부에에 투입한다.
In addition, the steam driving pump 400 is connected by the reloading water storage tank 10 and the fourth transfer pipe (P4). Accordingly, the steam driving pump 400 receives the cooling water from the injection tank 500 at the time of the total AC power supply, and supplies the cooling water into the pressure vessel 20 at the same time, and simultaneously stores the reload water. The reloading water is drawn from the tank 10 and introduced into the pressure vessel 20 into the pressurized reactor.

상기 습분분리기(600)는 상기 가압기 연결배관(100)의 관로상에 설치되는 것으로서, 좀 더 자세하게는 상기 개폐밸브(200)와 터빈(300) 사이의 가압기 연결배관(100) 관로상에 설치된다. 따라서, 가압기 연결배관(100)의 내부에서 유동하는 증기에 습분이 많이 포함되어 있는 경우 습분분리기(600)를 통하여 습분을 제거한 증기만을 상기 터빈(300)으로 보낸다.
The moisture separator 600 is installed on the pipeline of the pressurizer connecting pipe 100, and more specifically, is installed on the pressurizer connecting pipe 100 between the on-off valve 200 and the turbine 300. . Therefore, when a lot of moisture is contained in the steam flowing in the pressurizer connecting pipe 100, only the steam from which the moisture is removed through the moisture separator 600 is sent to the turbine 300.

10: 재장전수 저장탱크 20: 가압형원자로 압력용기
30: 순환배관 40: 가압기
50: 증기발생기 60: 원자로냉각재펌프
100: 가압기 연결배관 200: 개폐밸브
300: 터빈 400: 증기구동펌프
500: 인젝션탱크 600: 습분분리기
P1: 제1이송배관 P2: 제2이송배관
P3: 제3이송배관 P4: 제4이송배관10: reloading water storage tank 20: pressure vessel reactor
30: circulation pipe 40: pressurizer
50: steam generator 60: reactor coolant pump
100: pressurizer connection pipe 200: on-off valve
300: turbine 400: steam driven pump
500: injection tank 600: moisture separator
P1: 1st transfer piping P2: 2nd transfer piping
P3: 3rd transfer piping P4: 4th transfer piping

Claims (4)

가압형원자로 압력용기(20)에 일단과 타단이 연결되어 재장전수 저장탱크(10)로부터 상기 가압형원자로 압력용기(20) 내부로 공급된 재장전수를 순환시키는 순환배관(30)의 관로상에 설치되는 가압기(40)에 일단이 연결되어, 전체교류전원 상실시 상기 순환배관(30) 내부의 압력 하강에 의하여 재장전수로부터 발생된 증기를 유통시키는 가압기 연결배관(100)과;
상기 가압기 연결배관(100)의 관로상에 설치되어 전체교류전원 상실시 직류전원에 의하여 개방되는 개폐밸브(200)와;
상기 가압기 연결배관(100)의 타단에 연결되어 상기 개폐밸브(200)가 개방되었을 때 공급받은 증기에 의해 전력을 생산하는 터빈(300)과;
상기 터빈(300)으로부터 전력을 공급받아 작동하는 증기구동펌프(400)와;
상기 증기구동펌프(400)가 작동될 때 내부에 수용된 물이 상기 가압형원자로 압력용기(20) 내부로 투입되는 인젝션탱크(500);를 포함하여 구성된 것을 특징으로 하는 증기구동펌프를 이용한 피동안전주입계통.
One end and the other end are connected to the pressurized reactor pressure vessel 20 on the conduit of the circulation pipe 30 for circulating the reloading water supplied from the reloading water storage tank 10 into the pressurized reactor pressure vessel 20. One end is connected to the pressurizer 40 is installed, the pressurizer connecting pipe 100 for circulating the steam generated from the reloading water by the pressure drop inside the circulation pipe 30, the entire alternating current power supply;
An on / off valve (200) installed on a pipe of the pressurizer connecting pipe (100) and opened by a direct current power supply at all alternating current power;
A turbine 300 connected to the other end of the pressurizer connecting pipe 100 to produce electric power by steam supplied when the on-off valve 200 is opened;
A steam driving pump 400 operating by receiving electric power from the turbine 300;
When the steam driving pump 400 is operated when the water contained in the injection tank 500 is introduced into the pressure vessel 20 into the pressure-type reactor; blood transfer using a steam drive pump comprising a Infusion system.
청구항 1에 있어서,
상기 가압기 연결배관(100)을 통하여 터빈(300)으로 공급되어 터빈(300)의 전력생산에 이용된 후 액체로 상변화된 증기는 상기 재장전수 저장탱크(10)로 유입되는 것을 특징으로 하는 증기구동펌프를 이용한 피동안전주입계통.
The method according to claim 1,
Steam supplied to the turbine 300 through the pressurizer connecting pipe 100 and used for power generation of the turbine 300 and then phase-changed into a liquid flows into the reloading water storage tank 10. Total injection system during pumping.
청구항 1에 있어서,
전체교류전원 상실시 상기 증기구동펌프(400)는 상기 재장전수 저장탱크(10)로부터 재장전수를 끌어들여 상기 가압형원자로 압력용기(20) 내부로 투입하는 것을 특징으로 하는 증기구동펌프를 이용한 피동안전주입계통.
The method according to claim 1,
The steam drive pump 400 at the time of the total alternating power supply driven by the steam drive pump, characterized in that the reloading water from the reloading water storage tank (10) to draw into the pressure vessel 20 into the pressurized reactor. Safety injection system.
청구항 1에 있어서,
상기 개폐밸브(200)와 터빈(300) 사이의 가압기 연결배관(100) 관로상에는 습분분리기(600)가 더 설치되는 것을 특징으로 하는 증기구동펌프를 이용한 피동안전주입계통.The method according to claim 1,
Blood pressure pre-injection system using a steam drive pump, characterized in that the moisture separator 600 is further installed on the pressurizer connecting pipe 100 between the on-off valve 200 and the turbine 300.
KR1020120055546A 2012-05-24 2012-05-24 Passive safety injection system using vapor drive pump KR20130131757A (en)

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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20150117586A1 (en) * 2013-10-28 2015-04-30 BABCOCK & WILCOX mPOWER, INC Alternative safety function system for nuclear reactor
CN105679382A (en) * 2016-03-25 2016-06-15 上海核工程研究设计院 Nuclear power station primary loop main equipment direct connecting manner
WO2019135463A1 (en) * 2018-01-04 2019-07-11 Korea Atomic Energy Research Institute Safety injection device and nuclear power plant having the same

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20150117586A1 (en) * 2013-10-28 2015-04-30 BABCOCK & WILCOX mPOWER, INC Alternative safety function system for nuclear reactor
US9779840B2 (en) * 2013-10-28 2017-10-03 Bwxt Mpower, Inc. PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
US10726961B2 (en) 2013-10-28 2020-07-28 Bwxt Mpower, Inc. PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
US10950358B2 (en) 2013-10-28 2021-03-16 Bwxt Mpower, Inc. PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
CN105679382A (en) * 2016-03-25 2016-06-15 上海核工程研究设计院 Nuclear power station primary loop main equipment direct connecting manner
WO2019135463A1 (en) * 2018-01-04 2019-07-11 Korea Atomic Energy Research Institute Safety injection device and nuclear power plant having the same
US11348699B2 (en) 2018-01-04 2022-05-31 Korea Atomic Energy Research Institute Cooling water safety injection device powered by steam discharged during an accident and nuclear power plant having the same

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