KR101656361B1 - Reactor shutdown cooling using heat exchangers submerged within the water pool (or the water tank) around a nuclear reactor - Google Patents

Reactor shutdown cooling using heat exchangers submerged within the water pool (or the water tank) around a nuclear reactor Download PDF

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KR101656361B1
KR101656361B1 KR1020150074259A KR20150074259A KR101656361B1 KR 101656361 B1 KR101656361 B1 KR 101656361B1 KR 1020150074259 A KR1020150074259 A KR 1020150074259A KR 20150074259 A KR20150074259 A KR 20150074259A KR 101656361 B1 KR101656361 B1 KR 101656361B1
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cooling
reactor
heat exchanger
pump
water
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KR1020150074259A
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Korean (ko)
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이준
박천태
서재광
김교윤
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한국원자력연구원
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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
    • 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 nuclear reactor shutdown cooler using a heat exchanger submerged in a water bath around a nuclear reactor. More specifically, the nuclear reactor shutdown cooler using a heat exchanger submerged in a water bath around a nuclear reactor according to the present invention comprises: a water bath (10) arranged adjacent to a nuclear reactor (1) and having an apparatus coolant (C2) stored thereinside; and a shutdown cooling heat exchanger (20), installed inside the water bath (10) and submerged in the apparatus coolant (C2), for allowing a nuclear reactor coolant (C1) circulated to be supplied and the apparatus coolant (C2) of the water bath (10) to undergo heat-exchange. That is, the nuclear reactor shutdown cooler can submerge a shutdown cooling heat exchanger formed with multiple tubes in a water bath (or water tank) around a nuclear reactor for nuclear reactor shutdown cooling driving, and a nuclear reactor coolant passing the submerged tube bundle can perform shutdown cooling via heat exchange with an apparatus coolant.

Description

원자로 주변 수조(또는 물탱크)내 침수된 열교환기를 이용한 원자로 정지냉각장치{REACTOR SHUTDOWN COOLING USING HEAT EXCHANGERS SUBMERGED WITHIN THE WATER POOL (OR THE WATER TANK) AROUND A NUCLEAR REACTOR}BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor shutdown cooling apparatus using a submerged heat exchanger in a reactor water tank (or a water tank)

본 발명은 원자로의 정지냉각 운전을 위해 원자로 주변 수조(또는 물탱크)(이하 "수조"라고 함)에 정지냉각열교환기가 침수되어 원자로냉각재와 수조의 기기냉각수와의 열교환을 통하여 원자로를 정지냉각시키기 위한 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치에 관한 것이다.In the present invention, a stationary cooling heat exchanger is submerged in a reactor water tank (or a water tank) (hereinafter referred to as "water tank") for stopping and cooling operation of a reactor to cool the reactor through heat exchange between the reactor coolant and the cooling water The present invention relates to a reactor stop cooling apparatus using a submerged heat exchanger in a water tank around a nuclear reactor.

통상적으로 원자로는 운전 중 정지시 두 단계의 잔열제거 운전과정을 거친다.Typically, the reactor undergoes two stages of residual heat removal operation during shutdown during operation.

먼저 1단계 잔열제거 운전과정은 원자로냉각재(Reactor Coolant) 온도가 "약 310℃(원자로 정상운전 상태) → 약200℃(고온대기 상태)"로 냉각되는 과정이다.First, the first stage residual heat removal operation process is a process in which the reactor coolant temperature is cooled to about 310 ° C (normal operation state of the reactor) to about 200 ° C (high temperature standby state).

이 운전과정은 "고온 잔열제거 운전" 과정으로서 통상 "원자로 잔열제거(Reactor Residual Heat Removal) 운전"으로 정의되고 있으며, 이 경우 열교환 목적으로 증기발생기 또는 응축열교환기 기기가 이용되고 있다.This operation process is defined as "Reactor Residual Heat Removal Operation" as a "high temperature residual heat removal operation" process. In this case, a steam generator or a condensation heat exchanger device is used for heat exchange purposes.

원자로 정상시는 '증기발생기 → 터빈 → 증기발생기'로의 순환계통을 이용하며 반면 원자로 사고시는 '증기발생기 → 응축열교환기 → 증기발생기'로의 순환계통을 이용하는데 주요 특징은 원자로냉각을 위해 원자로냉각재(일차측 물=방사화된 물)가 아닌 급수/증기(이차측 물=방사화되지 않은 물)를 순환시킨다.In case of reactor accident, the circulation system from steam generator → turbine → steam generator is used, while in case of reactor accident, circulation system from 'steam generator → condensation heat exchanger → steam generator' is used. (Secondary water = non-radioactive water) rather than water / steam (secondary water = radioactive water).

이 운전과정은 통상적으로 자동으로 작동되는 경우가 대부분이다.This operation process is usually performed automatically.

다음으로 2단계 잔열제거 운전과정은 원자로냉각재 온도가 "약 200℃(고온대기 상태) → 약50℃(저온정지 이하 상태)"로 냉각되는 과정이다.Next, the second stage residual heat removal operation process is a process in which the reactor coolant temperature is cooled to "about 200 ° C. (high temperature standby state) → about 50 ° C. (low temperature stop state)".

이 운전과정은 "저온 잔열제거 운전" 과정으로서 통상 "원자로 정지냉각(Reactor Shutdown Cooling) 운전"으로 정의되고 있으며 이 경우 열교환 목적으로 정지냉각열교환기 기기가 이용되고 있다.This operation process is defined as "Reactor Shutdown Cooling Operation" as a "low temperature residual heat removal operation" process, in which a stationary cooling heat exchanger device is used for heat exchange purposes.

원자로 정상시 및 사고시 모두 '원자로 → 정지냉각열교환기 → 원자로'으로의 순환계통을 이용하는데 원자로냉각을 위해 원자로냉각재를 직접 순환시킨다.Both the normal reactor and the accident use the circulation system from 'reactor → stationary cooling heat exchanger → reactor' to circulate the reactor coolant directly for reactor cooling.

이 운정과정은 운전원이 수동작으로 작동시키는 경우가 보통이다.This operation routine is usually operated by the operator.

본 발명은 상기 두 단계의 잔열제거 운전과정중 2단계 잔열제거 운전과정인"원자로 정지냉각 운전"에 관한 것이다.The present invention relates to a two-stage residual heat removal operation process in the above-described two-stage residual heat removal operation, which is a "reactor stoppage cooling operation".

관련 종래기술로는 대한민국 공개특허특2001-0076566호(2001.08.16. 이하 '배경기술'이라 함) "원자로의 정지냉각 시스템"이 개시되어 있다.Related Background Art [0002] Korean Patent Laid-Open Publication No. 2001-0076566 (hereinafter referred to as "Background Art") discloses a "stationary cooling system of a nuclear reactor".

상기 배경기술은 원자로의 정지냉각 시스템에 관한 것으로, 정지냉각 펌프 및 열교환기를 거처 원자로 정지시 상온정지상태로 유지시키기 위한 정지냉각계통에 있어서, 정지냉각 펌프의 출력수를 그 펌프의 입력단으로 재순환시키도록 펌프 재순환용 오리피스 및 열교환기를 연결하여 펌프의 재순환 운전계통을 구성된다.The present invention relates to a quiescent cooling system for a nuclear reactor, and more particularly, to a quiescent cooling system for maintaining a quiescent cooling pump and a heat exchanger in a room-temperature quiescent state when a reactor is stopped, The pump recirculation orifice and the heat exchanger are connected to constitute the recirculation operation system of the pump.

또한 상기 정지냉각 펌프의 앞단에 연결된 밸브의 앞단에 상기 펌프의 고장시 정지냉각수를 격납용기 살수계통으로 보내기 위한 살수계통 연결밸브를 설치하며, 상기 격납용기 살수계통으로부터 상기 정지냉각 열교환기의 앞단으로 냉각수를 유입시키기 위한 살수계통 연결밸브를 설치하여 살수계통과 상호 보완적 작용을 수행하도록 구성하며, 재장전수조로부터 유입받는 냉각수를 상기 살수계통 연결밸브와 연결하고, 상기 정지냉각열교환기의 출력단에 있는 오리피스의 출력을 밸브를 통해서 상기 재저장수 수조로 연결하여 정지냉각모드가 아닌 정상 운전중에도 최대용량 시험을 수행할 수 있도록 구성하고, 정지냉각계통의 냉각수를 화학 및 체적계통의 필터 및 이온교환기 앞단에 있는 최종 유량 조절부의 앞단으로 체크밸브를 통해 연결하여 정화처리운전을 하도록 용수 정화 라인을 연결 구성되어 있다.A water sprinkling system connection valve is provided at the front end of the valve connected to the front end of the stationary cooling pump for sending the stationary cooling water to the storage container water sprinkling system when the pump fails and is connected to the front end of the stationary cooling water heat exchanger A sprinkling system connecting valve for introducing the cooling water is installed to perform complementary action with the sprinkling system and the cooling water flowing from the recharging water tank is connected to the sprinkling system connecting valve, And the output of the orifice is connected to the re-storing water tank through a valve so that the maximum capacity test can be performed even during normal operation other than the stop cooling mode. The cooling water of the stationary cooling system is supplied to a chemical and volumetric filter, Connected to the front end of the final flow control section at the front through a check valve And a water purifying line is connected to the purifying process operation.

그러나 상기 배경기술에서 사용되는 정지냉각용 열교환기는 셀-튜브타입 열교환기로서, 유입구와 유출부를 갖는 셀(또는 셀하우징)과, 이 셀 내부에 내장되는 다수의 튜브로 구성되어 튜브들에는 원자로냉각재가 통과하고, 기기냉각수는 셀의 유입구를 통하여 셀 내부로 유입되어 튜브들을 통과하는 원자로냉각재와 열교환 후, 셀의 유출부를 통하여 배출되도록 구성되어 있다.However, the stationary cooling heat exchanger used in the background art is a cell-tube type heat exchanger, which comprises a cell (or cell housing) having an inlet and an outlet, and a plurality of tubes embedded in the cell, And the device cooling water flows into the cell through the inlet of the cell, exchanges heat with the reactor coolant passing through the tubes, and is discharged through the outlet of the cell.

이러한 셀-튜브타입의 열교환기를 사용하는 종래의 정지냉각열교환기는 셀이 제거된 튜브타입의 열교환기를 사용할 수 없고, 또한 셀로 기기냉각수를 공급하여야 할 뿐만 아니라, 원자로 주변에 배치되는 수조나 물탱크 등을 활용하지 못하게 된다.The conventional stationary cooling heat exchanger using such a cell-tube type heat exchanger can not use a tube-type heat exchanger from which the cell is removed. In addition, it is necessary not only to supply the apparatus cooling water to the cell, but also to a water tank or a water tank You will not be able to use it.

따라서 본 발명에서는 튜브타입의 열교환기을 도입하고, 원자로 주변에 설치된 수조나 물탱크 등을 정지냉각에 활용할 수 있는 정지냉각장치를 개발하고자 한다.Therefore, in the present invention, a tube-type heat exchanger is introduced, and a stationary cooling device capable of utilizing a water tank or a water tank installed around the reactor for stationary cooling is developed.

대한민국 공개특허특1984-0002566호(1984.07.02.)Korean Patent Publication No. 1984-0002566 (July 2, 1984) 대한민국 공개특허특2001-0076566호(2001.08.16.)Korean Patent Publication No. 2001-0076566 (Aug. 16, 2001)

본 발명은 상기한 바와 같은 문제점을 해결하기 위해 안출된 것으로,SUMMARY OF THE INVENTION The present invention has been made to solve the above problems,

원자로 정지냉각 운전을 위해 원자로 주변에 위치하는 수조(또는 물탱크)(이하 "수조"라고 함)에 다수의 튜브로 구성되는 정지냉각열교환기를 침수시키고, 이렇게 침수된 튜브 다발을 통과하는 원자로냉각재가 수조의 기기냉각수와의 열교환을 통하여 정지냉각을 수행하고자 하는 것을 하나의 목적으로 한다.(Hereinafter referred to as "water tank") located in the vicinity of the reactor for immersing the stationary cooling heat exchanger made up of a plurality of tubes in such a manner that the reactor coolant passing through the flooded tube bundle It is one of the objects of the present invention to perform stationary cooling through heat exchange with apparatus cooling water in a water tank.

또한 본 발명은 원자로 주변에 설치되는 수조는 원자로 정지냉각 운전용도 이외에 다른 용도로도 활용하고자 하는 것을 또 하나의 목적으로 한다.It is another object of the present invention to utilize the water tank provided around the reactor for other purposes besides the operation for stopping and cooling the reactor.

나아가 본 발명은 정지냉각펌프의 가동불가 시(예. 고장이나 이상 발생 시 등), 정지냉각펌프 대신 원자로내장펌프 구동력을 이용하여 정지냉각을 일부 수행하고자 하는 것을 또 하나의 목적으로 한다.It is another object of the present invention to partially perform stop cooling by using a pump driving force built in the reactor instead of the stop cooling pump when the stop cooling pump can not be operated (for example, when a failure or abnormality occurs).

본 발명에 따른 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치는 원자로에 인접하여 배치되고, 기기냉각수가 저장된 수조; 및 상기 수조 내부에 내장되어 상기 기기냉각수에 침수되고, 순환 공급되는 원자로냉각재와 상기 수조의 기기냉각수를 열교환시키는 정지냉각열교환기를 포함하여 이루어진다.The reactor stop cooling apparatus using the submerged heat exchanger in the reactor water tank according to the present invention includes a water tank disposed adjacent to the reactor and storing the apparatus cooling water; And a stationary cooling heat exchanger built in the water tank for exchanging heat between the reactor coolant that is submerged in the apparatus cooling water and circulated and the apparatus cooling water in the water tank.

본 발명에 따른 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치는 정지냉각열교환기의 튜브 다발 전체가 원자로 주변에 배치되는 수조 내에 침수된 상태로 설치되어 원자로냉각재를 냉각시킬 수 있고, 튜브 타입의 열교환기를 사용함으로써 열교환기의 제작이나, 비용을 절감할 수 있다.The reactor stop cooling apparatus using the submerged heat exchanger in the reactor water tank according to the present invention can cool the reactor coolant by installing the entire tube bundle of the stationary cooling heat exchanger in a water tank disposed in the vicinity of the reactor, The heat exchanger can be manufactured and the cost can be reduced.

또한 본 발명에 따른 수조는 핵연료 교체 시작전에 원자로로부터 원자로냉각재를 빼내어 임시 저장하거나, 또는 핵연료 교체 완료 후, 수조 내에 임시 저장된 원자로냉각재를 원자로 내부로 보충하는데도 이용이 가능하다는 점에서 정기냉각 운전 용도 외에 다른 용도의 다목적 수조로도 활용이 가능하다.In addition, the water tank according to the present invention can be used to temporarily store nuclear fuel coolant from a reactor before nuclear fuel replacement is started, or to replenish reactor coolant temporarily stored in a water tank after nuclear fuel replacement is completed, It can also be used as a multipurpose water tank for other purposes.

아울러 본 발명은 정지냉각펌프의 가동불가 시(예. 고장이나 이상 발생 시 등), 정지냉각펌프 대신 원자로내장펌프 구동력을 이용하여 정지냉각을 일부 수행함으로써 정지냉각 운전을 보다 안정적으로 운용할 수 있다.Further, according to the present invention, when the stationary cooling pump can not be operated (for example, when a failure or an abnormality occurs), the stationary cooling operation can be performed more stably by partially performing the stationary cooling using the driving force of the reactor built- .

도 1은 본 발명에 따른 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치를 나타내는 개념도,
도 2는 본 발명에 따른 정지냉각장치에 따른 정지냉각계통(정지냉각펌프 라인 이용 경우)을 나타내는 계통도.
도 3은 본 발명에 따른 정지냉각장치에 따른 정지냉각계통을(정지냉각펌프 우회라인 이용 경우) 나타내는 계통도.1 is a conceptual diagram showing a reactor shutdown cooling apparatus using a submerged heat exchanger in a reactor water tank according to the present invention.
2 is a schematic diagram illustrating a stationary cooling system (in the case of using a stationary cooling pump line) according to the stationary cooling apparatus according to the present invention;
3 is a schematic diagram illustrating a stationary cooling system (in the case of using a stationary cooling pump bypass line) according to the stationary cooling apparatus according to the present invention;

이하에서는 본 발명에 따른 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치를 첨부된 도면을 참조하여 보다 자세하게 설명하기로 한다.Hereinafter, a reactor stop cooling apparatus using a submerged heat exchanger in a reactor water tank according to the present invention will be described in detail with reference to the accompanying drawings.

도 1에 도시된 바와 같이 격납용기(3) 내에는 원자로(1)가 설치되어 있으며 원자로(1) 내에는 핵연료 다발로 구성된 노심(2)이 위치하게 된다.As shown in FIG. 1, a reactor 1 is installed in a containment vessel 3, and a reactor core 2 composed of a bundle of nuclear fuel is placed in the reactor 1.

일체형원자로의 경우는 노심(2) 이외에 증기발생기(4)와 원자로내장펌프(31)도 원자로(1) 내에 내장된다. 원자로내장펌프(30)는 원자로냉각재(C1)를 원자로(1) 내부에서 순환시키는 펌프로서 원자로 정상 운전 및 정지냉각 운전 시 등 모든 원자로 운전시 항시 작동하는 펌프이며, 이에 의한 원자로 내 순환계통은 다음과 같이 이루어진다.In the case of the integral type reactor, the steam generator 4 and the reactor internal pump 31 are built in the reactor 1 in addition to the core 2. The reactor internal pump 30 is a pump that circulates the reactor coolant C1 in the reactor 1 and operates at all times during operation of all reactors such as normal operation and shutdown cooling operation of the reactor. .

먼저 노심(2) 상부 → 원자로내장펌프(31) 입구 → 원자로내장펌프(31) 출구 → 증기발생기(4) 상부 → 증기발생기(4) 하부 → 노심(2) 하부 → 노심(2) 상부로 순환하여 원자로냉각재(C1)를 순환시키게 된다.First, the upper part of the core 2, the inlet of the reactor internal pump 31, the outlet of the reactor internal pump 31, the upper part of the steam generator 4, the lower part of the steam generator 4, the lower part of the core 2, Thereby circulating the reactor coolant C1.

상기한 바와 같이 원자로내장펌프(31)가 설치되어 있는 일체형원자로는 정지냉각펌프(30)의 가동불가 시(예. 고장이나 이상 발생 시 등), 정지냉각펌프(30) 대신 원자로내장펌프(31) 구동력을 이용하여 정지냉각을 일부 수행할 수 있다.As described above, the integral nuclear reactor provided with the nuclear reactor built-in pump 31 can be used in place of the stationary cooling pump 30 when the stationary cooling pump 30 can not be operated (for example, when a failure or abnormality occurs) ) The stop cooling can be partially performed using the driving force.

전술한 바와 같은 정지냉각펌프(30)의 가동불가 시, 원자로내장펌프(31) 구동력을 이용하여 정지냉각을 수행하는 경우에 대한 설명은 도 3 설명 시 부연하기로 한다.The description of the case where the stationary cooling pump 30 is not operated and the stationary cooling is performed using the driving force of the reactor built-in pump 31 will be further described with reference to FIG.

도 1 내지 도 2에 도시된 바와 같이 본 발명에 따른 원자로 정지냉각장치는As shown in FIGS. 1 and 2, the reactor stop cooling apparatus according to the present invention includes:

원자로(1) 주변에 배치되고, 기기냉각수(C2)가 저장된 수조(10)와, 이 수조(10)에 내장되어 기기냉각수(C2)에 침수된 정지냉각열교환기(20)와, 정지냉각펌프(30) 또는 원자로내장펌프(31)를 포함하여 구성된다A stationary cooling heat exchanger 20 disposed in the vicinity of the reactor 1 and immersed in the apparatus cooling water C2 in the water tank 10, (30) or a nuclear reactor built-in pump (31)

먼저 도 1 내지 도 2에 도시된 바와 같이 본 발명에 따른 수조(10)는1 and 2, the water tank 10 according to the present invention includes:

원자로(1)가 설치된 격납용기(3) 인접 부근에 설치되고, 필요에 따라서는 여러 개로 구성될 수 있다.Is installed near the vicinity of the containment vessel (3) where the reactor (1) is installed, and may be composed of several as necessary.

이 수조(10) 내부에는 외부로부터 공급되는 냉각수, 즉 기기냉각수(C2)가 저장되고, 수조(10)에는 기기냉각수(C2)의 공급 배출을 위한 유출입부가 형성되며, 수조(10) 하부에는 기기냉각수 유입부(11)가, 수조(10) 상부에는 기기냉각수 유출부(13)가 배치된다.In the water tank 10, cooling water supplied from the outside, that is, equipment cooling water C2 is stored. An outlet portion for supplying and discharging the equipment cooling water C2 is formed in the water tank 10, The cooling water inflow portion 11 is disposed above the water tub 10, and the machine cooling water outflow portion 13 is disposed above the water tub 10.

이 경우 첨부된 도면에는 도시되지 않았지만 기기냉각수를 공급하기 위한 기기냉각수공급장치가 구비될 수 있고, 기기냉각수(C2)의 온도는 대략 45℃이하로 하는 것이 바람직하다.In this case, although not shown in the accompanying drawings, a device cooling water supply device for supplying the device cooling water may be provided, and the temperature of the device cooling water C2 is preferably about 45 ° C or lower.

다음으로 도 1 내지 도 2에 도시된 바와 같이 본 발명에 따른 정지냉각열교환기(20)는1 and 2, the stationary cooling heat exchanger 20 according to the present invention comprises:

수조(10)에 내장되어 기기냉각수(C2)에 침수된 상태로 배치되고, 원자로냉각재(C1)와 기기냉각수(C2)와의 열교환을 통하여 원자로냉각재(C1)를 냉각시키도록 구성된다.And is arranged in the water tank 10 so as to be immersed in the device cooling water C2 so as to cool the reactor coolant C1 through heat exchange between the reactor coolant C1 and the device cooling water C2.

이를 위한 정지냉각열교환기(20)는 튜브(21)타입 열교환기로서, 다수의 튜브(21)와, 튜브(21)들의 양단에 연결되어 튜브(21)들이 서로 이격된 상태로 고정되도록 하는 앤드플레이트와, 앤드플레이트에 연결되어 원자로냉각재(C1)의 유출입을 위한 유입부(11)와 유출부(13)가 형성된 헤더탱크(23)를 포함하여 구성된다.The stationary cooling heat exchanger 20 for this purpose is a tube 21 type heat exchanger and includes a plurality of tubes 21 and an end And a header tank 23 connected to the end plate and formed with an inflow portion 11 and an outflow portion 13 for inflow and outflow of the reactor coolant C1.

따라서 원자로(1)로부터 배출된 원자로냉각재(C1)는 유입측 헤더탱크(23)의 유입부(11)로 유입되어 각 튜브(21)들을 통과하면서 수조(10) 내의 기기냉각수(C2)와 열교환한 후, 유출측 헤더탱크(23)의 유출부(13)로 배출되고, 이렇게 냉각된 원자로냉각재(C1)는 원자로(1)로 다시 유입된다.The reactor coolant C1 discharged from the reactor 1 flows into the inlet portion 11 of the inlet side header tank 23 and flows through the tubes 21 while exchanging heat with the equipment coolant C2 in the water tank 10 And then discharged to the outlet 13 of the outlet side header tank 23. The cooled reactor coolant C1 flows into the reactor 1 again.

이 경우 원자로냉각재(C1)를 원자로(1)로부터 정지냉각열교환기(20) 및 원자로(1)로 순환 공급하여 원자로냉각재(C1)의 냉각라인(CL)을 구성하기 위해 정지냉각펌프(30)가 설치된다.In this case, the stationary cooling pump 30 is provided to circulate the reactor coolant C1 from the reactor 1 to the stationary cooling heat exchanger 20 and the reactor 1 to constitute the cooling line CL of the reactor coolant C1. Respectively.

또한 전술한 바와 같이 원자로내장펌프(31)가 설치되어 있는 일체형원자로는 정지냉각펌프(30)의 가동불가 시, 정지냉각펌프(30) 대신 원자로내장펌프(31) 구동력을 이용하여 정지냉각을 일부 수행할 수 있다.In addition, when the stationary cooling pump 30 can not be operated, the integral nuclear reactor in which the nuclear reactor built-in pump 31 is installed, as described above, performs stationary cooling by using the driving force of the nuclear reactor pump 31 instead of the stationary cooling pump 30 Can be performed.

따라서 원자로냉각재의 냉각라인(CL)은 원자로(1), 정지냉각펌프(30) 또는 원자로내장펌프(31), 정지냉각열교환기(20) 및 원자로(1)를 순환하면서 기기냉각수(C2)와 열교환을 통하여 정지냉각이 수행된다.The cooling line CL of the reactor coolant is circulated through the reactor 1, the stationary cooling pump 30 or the reactor internal pump 31, the stationary cooling heat exchanger 20 and the reactor 1, Stall cooling is performed through heat exchange.

냉각라인은 정지냉각펌프(30)가 가동되는 경우 원자로냉각재(C1)의 냉각순환을 담당하는 정지냉각펌프 라인(CL-1)과, 정지냉각펌프(30)가 가동불가한 경우 정지냉각펌프(30)를 우회하는 정지냉각펌프 우회라인(CL-2)으로 구성된다.The cooling line includes a stationary cooling pump line CL-1 for cooling and circulating the reactor coolant C1 when the stationary cooling pump 30 is operated and a stationary cooling pump line CL- And a stop cooling pump bypass line (CL-2) that bypasses the bypass line (30).

먼저 냉각라인 중 정지냉각펌프 라인(CL-1)은 정지냉각펌프(30)가 가동되는 경우 사용된다.First, the stop cooling pump line CL-1 in the cooling line is used when the stop cooling pump 30 is operated.

이 경우 도 2에 도시된 바와 같이 원자로냉각재(C1)가 정지냉각펌프(30) 측으로 흐르도록 정지냉각펌프 라인(CL-1)의 제1 밸브(32)를 개방하고, 정지냉각펌프 우회라인(CL-2)의 제2 밸브(32)는 폐쇄 상태로 둠으로써 정지냉각펌프 라인(CL-1)이 사용할 수 있게 된다.In this case, the first valve 32 of the stationary cooling pump line CL-1 is opened so that the reactor coolant C1 flows to the stationary cooling pump 30 side as shown in Fig. 2, and the stationary cooling pump bypass line The second valve 32 of the refrigerant circuit CL-2 is kept in a closed state so that the stationary cooling pump line CL-1 can be used.

정지냉각펌프 라인(CL-1)으로 유입된 원자로냉각재는(C1)는 정지냉각열교환기(20)로 유입되어 기기냉각수(C2)와 열교환을 통하여 냉각된 후 다시 원자로(1)로 순환된다.The reactor coolant introduced into the stationary cooling pump line CL-1 flows into the stationary cooling heat exchanger 20 through the heat exchanger C1 and circulates to the reactor 1 again after being cooled through heat exchange with the apparatus cooling water C2.

다음으로 냉각라인(CL) 중 정지냉각펌프 우회라인(CL-2)은 정지냉각펌프(30)가 가동불가한 경우 사용된다. 이 경우 원자로냉각재(C1)의 냉각순환은 원자로내장펌프(31) 구동력을 이용하여 수행된다. 이 경우 원자로냉각재(C1)의 냉각순환 유량은 원자로내장펌프(31) 구동력에 의해 결정된다.Next, the stopping cooling pump bypass line CL-2 in the cooling line CL is used when the stopping cooling pump 30 can not be operated. In this case, the cooling circulation of the reactor coolant (C1) is performed using the driving force of the reactor internal pump (31). In this case, the cooling circulation flow rate of the reactor coolant (C1) is determined by the driving force of the reactor internal pump (31).

이 경우 도 3에 도시된 바와 같이 원자로냉각재(C1)가 정지냉각펌프(30)를 우회하도록 정지냉각펌프 우회라인(CL-2)의 제2 밸브(33)를 개방하고, 이어 정지냉각펌프 라인(CL-1)의 제1 밸브(32)를 폐쇄함으로서 정지냉각펌프 우회라인(CL-2)이 사용할 수 있게 된다. In this case, as shown in FIG. 3, the second valve 33 of the shutdown cooling pump bypass line CL-2 is opened so that the reactor coolant C1 bypasses the static cooling pump 30, The first valve 32 of the refrigerant circuit CL-1 is closed so that the stopping cooling pump bypass line CL-2 can be used.

정지냉각펌프 우회라인(CL-2)으로 유입된 원자로냉각재는(C1)는 정지냉각열교환기(20)로 유입되어 기기냉각수(C2)와 열교환을 통하여 냉각된 후 다시 원자로(1)로 순환된다.The reactor coolant introduced into the stationary cooling pump bypass line CL-2 flows into the stationary cooling heat exchanger 20 through the heat exchange with the apparatus cooling water C2 and then circulated to the reactor 1 again .

또한 튜브타입의 열교환기를 사용하는 경우에는 수조(10) 내의 기기냉각수(C2)가 모두 상실되는 경우에도 튜브(21)가 공기 중으로 노출되기 때문에 공랭식 냉각이 가능하다는 점에서 또 다른 의의가 있다.Further, in the case of using a tube type heat exchanger, there is another significance in that air cooling can be performed because the tube 21 is exposed to the air even when all the apparatus cooling water C2 in the water tank 10 is lost.

상기한 바와 같이 구성되는 원자로 정지냉각장치는 종래의 셀-튜브타입의 열교환기 대신에 튜브타입의 열교환기를 이용하여 정지냉각 운전을 수행할 수 있게 된다.The reactor stop cooling apparatus configured as described above can perform the stationary cooling operation by using a tube type heat exchanger instead of the conventional cell-tube type heat exchanger.

또한 원자로 주변에 설치되는 수조나 물탱크를 냉각조로 활용할 수 있다는 점에서 유리할 뿐만 아니라, 수조나 물탱크를 정지냉각 운전 이외에 다른 용도로 활용이 가능하다.In addition, it is advantageous in that a water tank or a water tank installed around the reactor can be used as a cooling tank, and a water tank or a water tank can be used for other purposes besides the stationary cooling operation.

예컨대 핵연료 교체 시작 전에는 원자로로부터 원자로냉각재를 빼내어 수조나 물탱크에 임시로 저장하거나, 또는 핵연료 교체 완료 후, 수조나 물탱크 내에 임시 저장된 원자로냉각재를 원자로로 보충하는데도 활용이 가능하다.For example, it is possible to extract the reactor coolant from the reactor temporarily before starting to replace the fuel, temporarily store it in the water tank or the water tank, or to supplement the reactor coolant temporarily stored in the water tank or the water tank after completion of the fuel exchange.

이상에서 첨부된 도면을 참조하여 본 발명인 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치를 설명함에 있어 특정 형상 및 방향을 위주로 설명하였으나, 본 발명은 당업자에 의하여 다양한 변형 및 변경이 가능하고, 이러한 변형 및 변경은 본 발명의 권리범위에 포함되는 것으로 해석되어야 한다.While the present invention has been particularly shown and described with reference to exemplary 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. Such variations and modifications are to be construed as being included within the scope of the present invention.

CL : 냉각라인 CL-1 : 정지냉각펌프 라인
CL-2 : 정지냉각펌프 우회라인 C1 : 원자로냉각재
C2 : 기기냉각수
1 : 원자로 2 : 노심
3 : 격납용기 4 : 증기발생기
10 : 수조(또는 물탱크)
11 : 기기냉각수 유입부 13 : 기기냉각수 유출부
20 : 정지냉각열교환기
21 : 튜브 23 : 헤더탱크
30 : 정지냉각펌프 31 : 원자로내장펌프
32 : 제1 밸브 33 : 제2 밸브CL: Cooling line CL-1: Stopping cooling pump line
CL-2: Stop cooling pump bypass line C1: Reactor coolant
C2: Chilled water
1: Reactor 2: Core
3: Storage vessel 4: Steam generator
10: Water tank (or water tank)
11: Device cooling water inlet 13: Device cooling water outlet
20: stationary cooling heat exchanger
21: tube 23: header tank
30: Stopping cooling pump 31: Built-in reactor pump
32: first valve 33: second valve

Claims (5)

원자로(1)에 인접하여 배치되고, 기기냉각수(C2)가 저장된 수조(10);
상기 수조(10) 내부에 내장되어 상기 기기냉각수(C2)에 침수되고, 순환 공급되는 원자로냉각재(C1)와 상기 수조(10)의 기기냉각수(C2)를 열교환시키는 정지냉각열교환기(20); 및
상기 원자로(1)로부터 상기 정지냉각열교환기(20)로 원자로냉각재(C1)를 순환 공급하여 냉각라인(CL)을 구성하기 위한 정지냉각펌프(30) 및 원자로내장펌프(31)를 포함하되,
상기 냉각라인(CL)은, 상기 정지냉각펌프(30)가 가동되는 경우 원자로냉각재(C1)의 냉각순환을 담당하는 정지냉각펌프 라인(CL-1)과, 상기 정지냉각펌프(30)가 가동불가한 경우 상기 원자로내장펌프(31) 구동력을 이용하여 정지냉각펌프(30)를 우회하는 정지냉각펌프 우회라인(CL-2)을 포함하여 이루어진 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치.
A water tank 10 disposed adjacent to the reactor 1 and storing the device cooling water C2;
A stationary cooling heat exchanger (20) built in the water tank (10) for exchanging heat between the reactor coolant (C1) immersed in the apparatus cooling water (C2) and circulated and the apparatus cooling water (C2) of the water tank (10); And
A stationary cooling pump 30 and a reactor internal pump 31 for circulating a reactor coolant C1 from the reactor 1 to the stationary cooling heat exchanger 20 to constitute a cooling line CL,
The cooling line CL includes a stationary cooling pump line CL-1 for cooling and circulating the reactor coolant C1 when the stationary cooling pump 30 is operated, And a stop cooling pump bypass line (CL-2) bypassing the stop cooling pump (30) by using the driving force of the reactor built-in pump (31) .
제 1 항에 있어서,
상기 정지냉각열교환기(20)는 튜브타입 열교환기인 것을 특징으로 하고 기기냉각수(C2)에 침수되고 기기냉각수(C2)로 열교환되는 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치.
The method according to claim 1,
The stationary cooling heat exchanger (20) is a tube type heat exchanger. The stationary cooling heat exchanger (20) is immersed in the apparatus cooling water (C2) and heat exchanged with the apparatus cooling water (C2).
삭제delete 삭제delete 제 1 항에 있어서,
상기 정지냉각펌프(30)가 가동불가한 경우 상기 원자로내장펌프(31) 구동력을 이용하여 정지냉각을 수행하는 것을 특징으로 하는 원자로 주변 수조내 침수된 열교환기를 이용한 원자로 정지냉각장치.The method according to claim 1,
Wherein the stop cooling is performed using the driving force of the reactor built-in pump (31) when the stationary cooling pump (30) can not be operated.
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KR101731782B1 (en) * 2016-10-07 2017-05-02 (주)해우엔지니어링건축사사무소 Firewater managing apparatus
KR20210044067A (en) * 2019-10-14 2021-04-22 한국전력기술 주식회사 Apparatus for controlling reactor coolant inventory in Reactor Coolant System at an emergency event

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KR20210044067A (en) * 2019-10-14 2021-04-22 한국전력기술 주식회사 Apparatus for controlling reactor coolant inventory in Reactor Coolant System at an emergency event
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