KR100448876B1 - Emergency feed water system in nuclear power plant - Google Patents
Emergency feed water system in nuclear power plant Download PDFInfo
- Publication number
- KR100448876B1 KR100448876B1 KR10-2001-0069865A KR20010069865A KR100448876B1 KR 100448876 B1 KR100448876 B1 KR 100448876B1 KR 20010069865 A KR20010069865 A KR 20010069865A KR 100448876 B1 KR100448876 B1 KR 100448876B1
- Authority
- KR
- South Korea
- Prior art keywords
- water supply
- supply system
- emergency water
- emergency
- power plant
- Prior art date
Links
Classifications
-
- 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
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
본 발명은 전원으로 가동되는 비상급수계통에서 전원의 차단 또는 오동작으로 냉각수를 공급하지 못하여 발생하는 원자로 냉각재 계통의 방사능 누출 등을 예방하기 위해 독립적으로 구동되는 급수펌프를 연결하여 급수 기능을 향상시키고, 또한 디젤 등으로 구동되어 전원이 없이도 구동될 수 있는 비상급수 펌프를 구비하여 증기발생기로 안정적으로 급수를 공급할 수 있는 원자력 발전소의 비상급수 시스템에 관한 것이다.The present invention improves the water supply function by connecting a water pump independently driven to prevent radiation leakage of the reactor coolant system caused by the failure of supplying cooling water due to the interruption or malfunction of the power supply in the emergency water supply system operated by the power source, In addition, the present invention relates to an emergency water supply system of a nuclear power plant, which can be stably supplied with a steam generator by having an emergency water supply pump driven by diesel and driven without power.
본 발명은 원자력 발전소에서 비상급수를 공급하는데 있어서, 급수를 저장하여 공급하는 비상급수 탱크, 비상급수 탱크에서 급수를 공급받아 증기발생기로 제공하는 급수계통, 급수계통의 이상이 발생 시에 비상급수를 공급하는 비상급수계통, 급수계통과 비상 급수계통으로부터 비상급수를 공급받는 증기발생기를 포함하는 것을 특징으로 한다.The present invention is to supply emergency water in the nuclear power plant, the emergency water tank for storing and supplying the water supply, the water supply system supplied to the steam generator to receive the water supply from the emergency water supply tank, emergency water supply when the abnormality of the water supply system occurs It characterized in that it comprises a steam generator for receiving emergency water supply from the emergency water supply system, the water supply system and the emergency water supply system to supply.
Description
본 발명은 원자력발전소의 비상급수 시스템에 관한 것으로, 특히 전원으로 가동되는 비상급수계통에서 전원의 차단 또는 오동작으로 냉각수를 공급하지 못하여 발생하는 원자로 냉각재 계통의 방사능 누출 등을 예방하기 위해 독립적으로 구동되는 급수펌프를 연결하여 비상급수 기능을 향상시키고, 또한 디젤 등으로 구동되어 전원이 없이도 구동될 수 있는 비상급수 펌프를 구비하여 증기발생기로 안정적으로 급수를 공급할 수 있는 원자력 발전소의 비상급수 시스템에 관한 것이다.The present invention relates to an emergency water supply system of a nuclear power plant, and in particular, is independently driven to prevent radiation leakage of the reactor coolant system caused by the failure to supply the coolant due to the interruption or malfunction of the power supply in the emergency water supply system operated by the power source. It is related with emergency water supply system of nuclear power plant which can connect water feed pump to improve emergency water supply function and also can supply water to steam generator stably with emergency water supply pump which can be driven without diesel power by being driven by diesel. .
일반적으로 원자력 발전소는 크게 원자로를 중심으로 한 핵증기 공급계통(NSSS : nuclear steam supply system)과 증기를 공급받아 발전기를 구동시키는 터빈, 발전기계통 그리고 비상급수 등 기타 부수 설비로 구분된다.In general, a nuclear power plant is divided into a nuclear steam supply system (NSSS) centered on a nuclear reactor, and a turbine, a generator system, and other ancillary facilities such as emergency water supply, which operate a generator by receiving steam.
정상적인 원자력 발전중(300 ℃) 원자로에서 발생하는 열제거는 증기발생기에 물을 1차적으로 공급하는 급수계통과 정상적인 급수의 공급이 불능시에는 물을 2차적으로 공급하는 비상급수계통, 원자로 냉각재 계통이 177 ℃ 이하 시에 열을 제거하는 원자로 냉각재 계통과 직접 연결된 잔열제거 계통으로 구성된다.Heat removal from a nuclear reactor during normal nuclear power generation (300 ℃) includes a water supply system that supplies water to the steam generator first, and an emergency water supply system that supplies water secondly when normal water supply is not available, and a reactor coolant system. It consists of a residual heat removal system directly connected to the reactor coolant system that removes heat below 177 ° C.
비상급수 계통은 급수계통이 사고 등으로 인하여 급수를 공급하지 못할 때, 잔열제거 계통이 작동하는 시점까지의 원자로 냉각기간 동안 증기발생기로 비상급수를 공급하며, 잔열제거 계통이 운전불능시에는 비상급수 계통에서 계속적인 비상급수를 공급한다. 비상급수 계통은 비상급수펌프, 밸브 및 배관 등으로 구성된다.The emergency water supply system supplies emergency water to the steam generator during the reactor cooling period until the residual heat removal system is operated when the water supply system cannot supply water due to an accident, etc., and the emergency water supply when the residual heat removal system is inoperable. Supply continuous emergency water from the system. Emergency water supply system consists of emergency water pump, valves and piping.
원자력 발전소의 비상급수계통은 운전 중의 급수상실이나 증기발생기의 튜브누설, 원자로 냉각재의 상실사고 및 발전소 완전전원상실(교류전원 완전상실, 직류전원 이용가능) 등의 사고 시에 원자로 냉각재 계통의 열을 제거하고 원자로 노심이 냉각제로부터 노출되는 것을 방지하기 위하여 증기발생기에 비상급수를 공급하는 독립적인 기능을 수행하는 것이다.The emergency water supply system of a nuclear power plant heats up the reactor coolant system in the event of an accident such as a water supply loss during operation, a tube leak of a steam generator, a loss of reactor coolant, or a complete loss of power plant (complete loss of AC power, DC power available). It is an independent function to supply emergency water to the steam generator to remove it and to prevent the reactor core from being exposed from the coolant.
원자력 발전소의 주요 구조물의 배치상태는 중앙에 원자로 용기가 위치하며, 양측으로는 증기발생기가 각각 설치되어 있고 고온관과 저온관에는 각각 물을 순환시켜주기 위한 펌프가 구비되며 일차측 고온관에는 별도의 폐쇄관로 내의 압력을 조절하도록 하는 압력조절 장치의 가압기가 설치되어 있으며, 증기발생기에는 비상급수계통의 비상급수장치가 연결되어 있다.The reactor structure is located at the center of the nuclear power plant, and the steam generator is installed on both sides, and the hot and cold pipes are equipped with a pump to circulate water, respectively. The pressurizer of the pressure regulating device is installed to regulate the pressure in the closed pipe of the steam generator, and the emergency water supply system of the emergency water supply system is connected to the steam generator.
도 1은 종래의 비상급수 시스템을 개략적으로 도시한 것이다.Figure 1 schematically shows a conventional emergency water supply system.
종래의 비상급수 시스템(10)은 두 개의 서브 시스템(11,12)으로 이루어진다.The conventional emergency water supply system 10 consists of two subsystems 11 and 12.
하나의 서브시스템(11,12)은 각각 비상급수탱크(13,16), 급수계통(14,17), 증기발생기(15,18)와 배관, 밸브 등으로 구성된다. 즉 원자력 발전소의 비상급수 시스템은 두 대의 서브 시스템이 독립적으로 작동하며, 서로 비상급수를 공급하는 데에 있어서 상호 연관적인 작동을 하지 못한다.One subsystem (11, 12) is composed of emergency water supply tank (13, 16), water supply system (14, 17), steam generators (15, 18), piping, valves and the like, respectively. In other words, the emergency water supply system of a nuclear power plant is operated by two sub-systems independently and does not correlate with each other in supplying emergency water supply.
한편, 도 2는 도 1의 비상급수 시스템의 급수계통(14,17)과 증기발생기(15, 18)의 상세한 블럭도이다.2 is a detailed block diagram of the water supply system 14 and 17 and the steam generators 15 and 18 of the emergency water supply system of FIG. 1.
급수계통(14, 17)은 전동기구동 펌프(20)와 증기구동펌프(22)를 구비하며,각각의 배관에는 밸브(21, 23)가 구비된다. 전동기구동 펌프(20)와 증기구동펌프(22)의 배관은 서로 연결되어서 비상급수 탱크에 연결되어 급수를 받는다. 또한, 전동기구동 펌프(20)와 증기구동펌프(22)의 배관에 구비된 밸브(21, 23)도 서로 연결되어 하나의 출구로 급수를 공급한다. 하나의 출구는 격납건물 내부에 있는 밸브(24)와 연결되며, 배관을 통하여 증기발생기(15, 18)로 비상급수를 공급하는 것이다.The water supply system 14 and 17 includes an electric drive pump 20 and a steam drive pump 22, and valves 21 and 23 are provided in the respective pipes. Pipes of the electric drive pump 20 and the steam drive pump 22 is connected to each other and connected to the emergency water supply tank receives water. In addition, the valves 21 and 23 provided in the pipes of the electric drive pump 20 and the steam drive pump 22 are also connected to each other to supply water to one outlet. One outlet is connected to the valve 24 in the containment building and supplies emergency water to the steam generators 15 and 18 through piping.
비상급수 공급시에는 비상급수 탱크(13, 16)에서 물을 공급받아 급수계통(14, 17)의 전동기구동 펌프(20)와 증기구동펌프(22)를 거쳐서 배관과 밸브를 통하여 증기발생기(15, 18)에 비상급수를 공급한다.In the case of emergency water supply, water is supplied from the emergency water supply tanks 13 and 16 through the electric drive pump 20 and the steam drive pump 22 of the water supply system 14 and 17 through a pipe and a valve. , 18) supply emergency water supply.
한편, 종래의 비상급수 시스템에서 사용되는 증기구동 펌프(22)의 경우 장기간 동안의 원자로 냉각재 상실사고가 발생하면, 복구하는 기간 동안 증기발생기(15, 18)의 압력이 상실되어 증기구동 펌프(22)는 운전이 불능 상태가 되어 비상급수를 공급하지 못하는 문제점이 발생할 수 있다.Meanwhile, in the case of the steam driving pump 22 used in the conventional emergency water supply system, if the reactor coolant loss accident occurs for a long time, the pressure of the steam generators 15 and 18 is lost during the recovery period, and the steam driving pump 22 ) May cause a problem in that it is impossible to supply emergency water supply due to the inability to operate.
또한, 운전가능한 전동기구동 펌프(20)에서 단일고장(Single Failure) 적용 시에 종래의 비상급수 시스템은 독립적으로 동작하며 상호연결 배관이 없기 때문에 운전가능한 전동기구동 펌프(20)로 누설측의 증기발생기 튜브를 장기간 증기발생기의 수위 아래로 잠길 수 없어 1차 측에서 2차 측으로 누설되는 방사능을 감소시킬 수 없는 문제점이 있다.In addition, when a single failure is applied in the operable electric motor driven pump 20, the conventional emergency water supply system operates independently and there is no interconnection pipe, so the steam generator on the side of the electric motor driven pump 20 is operable. There is a problem in that the tube can not be locked below the water level of the steam generator for a long time can not reduce the radiation leakage from the primary side to the secondary side.
이상과 같이, 종래의 비상급수 시스템은 원자력 발전소에서 완전 전원을 상실 시에는 전동기구동 펌프(20)는 동작할 수 없으며, 또한, 장기간의 냉각 시에는증기발생기의 압력이 상실되어 증기구동 펌프(22)가 운전불능 상태가 되므로 원자력 발전소의 핵연료 손상 및 방사능 누출을 초래할 수 있는 문제점이 있다.As described above, in the conventional emergency water supply system, the electric drive pump 20 cannot operate when full power is lost in the nuclear power plant, and the pressure of the steam generator is lost during long-term cooling, and thus the steam drive pump 22 ) Becomes inoperable and there is a problem that can lead to nuclear fuel damage and radiation leakage of the nuclear power plant.
또한, 격납건물 외부에 위치한 비상급수 계통에서 증기발생기가 위치한 격납건물을 관통하여 설치된 역지밸브가 고장이 발생하면 비상급수계통의 비상급수 공급기능을 모두 상실하는 문제점이 있다.In addition, when the check valve installed through the containment building where the steam generator is located in the emergency water supply system located outside the containment building has a problem, all of the emergency water supply function of the emergency supply system is lost.
상술한 바와 같이 종래의 비상급수 계통은 증기발생기 튜브누설 발생시 원자로 냉각재 계통의 방사능 누출을 증기발생기를 통하여 2차측으로 증대시키고, 완전 전원 상실(SBO : Station Black Out)시는 원자로 냉각재 계통을 증기발생기를 통하여 냉각할 수 없으므로 핵연료 손상 가능성이 증대되어 원자력 발전소의 안전성을 저하시키는 문제점이 있다.As described above, the conventional emergency water supply system increases the leakage of radiation from the reactor coolant system to the secondary side when the steam generator tube leakage occurs, and the reactor coolant system is changed to the reactor coolant system at the time of complete power loss (SBO: Station Black Out). There is a problem in that the possibility of nuclear fuel damage is increased because it can not be cooled through to reduce the safety of the nuclear power plant.
본 발명은 상술한 바와 같은 문제점을 해결하기 위한 것으로, 원자력 발전소의 안정성 향상 및 원자로 냉각재 계통의 방사능 누출을 차단하기 위한 비상급수 시스템으로 시스템과 두 개의 서브 시스템간의 상호연결배관 및 수동밸브를 구비하여 서로 연동하여 사용할 수 있어서 비상급수에 효율이 증대되며, 원자력 발전소의 완전 전원 상실로 인하여 전동기구동펌프와 증기구동펌프가 작동하지 못하여 급수를 공급하지 못하는 상황이 발생하여도 전원이 없이도 구동이 가능한 디젤구동 펌프, 배관 및 수동밸브를 구비하여 비상급수를 공급하는 것이다.The present invention is to solve the problems as described above, with an emergency water supply system for improving the stability of the nuclear power plant and to prevent radiation leakage of the reactor coolant system having an interconnection pipe and a manual valve between the system and the two subsystems It can be used in conjunction with each other to increase the efficiency of emergency water supply, and the diesel can be driven without power even when there is a situation in which the electric power supply pump and the steam driving pump cannot operate and supply water due to the complete power loss of the nuclear power plant. It is equipped with drive pump, piping and manual valve to supply emergency water supply.
또한, 원자력 발전소의 운전중 급수상실, 증기발생기 튜브누설, 원자로냉각재 상실사고 및 원자력 발전소 완전 전원 상실의 사고시에 증기발생기에 비상급수를 계속적으로 공급하여 원자로 냉각재 계통을 냉각하여 원자로 및 연료손상을 방지하고 증기발생기를 통한 2차측으로 방사능 누출을 차단하여 안전하게 원자력 발전소를 가동시킬 수 있는 원자력발전소의 비상급수 시스템의 제공을 그 목적으로 한다.In addition, in case of water supply loss during operation of nuclear power plant, steam generator tube leakage, nuclear reactor coolant accident and nuclear power plant total power loss, emergency water supply is continuously supplied to steam generator to prevent nuclear reactor and fuel damage. The purpose is to provide an emergency water supply system for nuclear power plants that can safely operate nuclear power plants by blocking radioactive leakage to the secondary side through steam generators.
도 1은 종래의 비상급수 계통을 도시한 블럭도.1 is a block diagram showing a conventional emergency water supply system.
도 2는 도 1의 비상급수 계통의 상세 블럭도.2 is a detailed block diagram of the emergency water supply system of FIG.
도 3은 본 발명의 비상급수 계통을 도시한 블럭도.Figure 3 is a block diagram showing an emergency water supply system of the present invention.
도 4는 도 3의 비상급수 계통의 상세 블록도.4 is a detailed block diagram of the emergency water supply system of FIG.
<도면의 주요 부분에 대한 설명>Description of the main parts of the drawing
10 : 종래의 비상급수 시스템 11 : 제 1 비상급수로10: conventional emergency water supply system 11: the first emergency water supply
12 : 제 2 비상급수로 13, 16, 30, 34 : 비상급수 탱크12: 2nd emergency water supply passage 13, 16, 30, 34: emergency water supply tank
14, 17, 31, 35 : 급수계통 15, 18, 32, 36 : 증기발생기14, 17, 31, 35: water supply system 15, 18, 32, 36: steam generator
20 : 전동기구동 펌프 21, 23, 24, 41, 45, 46, 47, 48 : 밸브20: electric drive pump 21, 23, 24, 41, 45, 46, 47, 48: valve
22 : 증기구동 펌프 33 : 비상급수 시스템22: steam driven pump 33: emergency water supply system
40 : 디젤구동 펌프 42, 43 : 배관연결점40: diesel driving pump 42, 43: pipe connection point
44 : 상호연결배관44: interconnection piping
상술한 바와 같은 목적을 달성하기 위한 본 발명은 원자력 발전소에서 비상급수를 공급하는데 있어서, 급수를 저장하여 공급하는 비상급수 탱크, 비상급수 탱크에서 급수를 공급받아 증기발생기로 제공하는 급수계통, 급수계통의 이상이 발생 시에 비상급수를 공급하는 비상급수계통, 급수계통과 비상 급수계통으로부터 급수를 공급받는 증기발생기를 포함한다.The present invention for achieving the above object in the emergency power supply in the nuclear power plant, the emergency water supply tank for storing and supplying the water supply, the water supply system for supplying the water supply from the emergency water supply tank to the steam generator, water supply system It includes an emergency water supply system, a water supply system and a steam generator supplied with water from the emergency water supply system when the abnormality occurs.
또한, 급수계통은 전동기구동펌프와 증기구동펌프의 각각의 배관수단과 배관수단을 서로 연결하는 제 1 상호연결 배관수단, 각각의 배관수단에 연결된 각각의 밸브 수단과 밸브수단을 상호연결하여 증기발생기로 비상급수하는 서브시스템 A와, 다른 비상급수 탱크에 연결된 전동기구동펌프와 증기구동펌프의 각각의 배관수단과 배관수단을 서로 연결하는 제 2 상호연결 배관수단, 각각의 배관수단에 연결된 각각의 밸브 수단과 밸브 수단을 상호연결하여 증기발생기로 비상급수하는 서브시스템 B를 특징으로 한다.In addition, the feed water system is the first interconnection piping means for connecting the respective piping means and piping means of the electric drive pump and the steam drive pump, each valve means and valve means connected to each piping means by interconnecting the steam generator A second interconnecting piping means for connecting the piping means and the piping means of the electric motor driven pump and the steam driven pump connected to the other emergency water supply tank, and each valve connected to each piping means Subsystem B, which interconnects the means and the valve means to emergency water supply to the steam generator.
또한, 본 발명의 비상급수 계통은 제 1 상호연결 배관수단과 제 2 상호연결배관수단을 상호연결하는 제 3 상호연결 배관수단, 제 3 상호연결 배관수단에 연결된 비상 급수펌프와 밸브를 포함하며, 비상급수 펌프는 전원이 상실되어도 급수를 공급할 수 있는 디젤구동 급수 펌프이며, 밸브는 비상급수밸브, 역지밸브, 수동밸브로 구비되는 것을 특징으로 한다.Further, the emergency water supply system of the present invention includes a third interconnect piping means for interconnecting the first interconnect piping means and the second interconnect piping means, an emergency water pump and a valve connected to the third interconnect piping means, Emergency water supply pump is a diesel-driven water supply pump that can supply water even if the power is lost, the valve is characterized in that the emergency water supply valve, check valve, manual valve is provided.
이하, 본 발명에 따른 실시 예를 첨부한 도면을 참조하여 상세히 설명하면 다음과 같다.Hereinafter, exemplary embodiments of the present invention will be described in detail with reference to the accompanying drawings.
도 3은 본 발명에 따른 비상급수 계통을 도시한 블럭도이다.3 is a block diagram showing an emergency water supply system according to the present invention.
본 발명의 비상급수계통은 서브시스템간의 배관을 서로 연결하여 다른 서브시스템에서 고장이 발생시에도 비상급수를 할 수 있으며, 또한, 원자력 발전소의 원자로냉각재 상실사고 및 원자력 발전소의 완전 전원 상실의 사고 시에도 증기발생기에 계속적으로 비상급수를 공급하여 안전하게 원자력 발전소를 가동시킬 수 있는 비상급수 시스템이다.Emergency water supply system of the present invention by connecting the pipes between the subsystems can be emergency water supply in the event of a failure in the other subsystems, and also in the case of a nuclear power plant reactor coolant accident and a nuclear power plant complete power loss accident. It is an emergency water supply system that can safely operate a nuclear power plant by continuously supplying emergency water supply to a steam generator.
물을 공급하는 비상급수 탱크(30, 34)와 각각의 급수계통(31, 35)과 두 개의 급수 계통을 연결하는 배관연결점(42, 43)과 상술한 비상시에도 급수를 공급할 수 있는 비상급수 계통(33)과 증기발생기(32, 36)로 이루어 진다.Emergency water supply tank (30, 34) for supplying water, pipe connection points (42, 43) for connecting each of the water supply system (31, 35) and two water supply systems, and emergency water supply system that can supply water in the above-mentioned emergency (33) and the steam generator (32, 36).
본 발명의 비상급수 탱크(30, 34)와 급수계통(31, 35)을 이루는 전동기구동펌프와 증기구동펌프, 디젤구동펌프는 각각 증기발생기(32, 36)에 비상급수를 공급하는데에 있어서 정상동작 시에는 비상급수 동작을 독립적으로 100% 할 수 있다.The electric drive pump, the steam drive pump, and the diesel drive pump forming the emergency water supply tanks 30 and 34 and the water supply system 31 and 35 of the present invention are normal in supplying emergency water supply to the steam generators 32 and 36, respectively. In operation, emergency water supply operation can be performed 100% independently.
비상급수 시스템은 서브 시스템간의 급수계통(31, 35)을 연결하여 사용하므로써 하나의 서브시스템에서 고장이 발생시에는 다른 서브시스템에서 비상급수를원활히 공급할 수 있다.The emergency water supply system can connect the water supply systems 31 and 35 between the subsystems so that in case of a failure in one subsystem, emergency water can be supplied from another subsystem.
또한, 두 개 서브시스템의 급수계통(31, 35)에서 사고 등으로 인한 고장이 발생되어도 비상급수 계통(33)이 작동하므로 안전하게 원자력 발전소의 증기발생기를 냉각시킬 수 있는 것이다.In addition, the emergency water supply system 33 operates even if a failure occurs due to an accident in the water supply systems 31 and 35 of the two subsystems, so that the steam generator of the nuclear power plant can be safely cooled.
한편, 도 4는 도 3의 상세 블럭도로, 급수계통(31, 35)과 비상급수 계통(33)과 증기발생기(32, 36)를 도시한 것이다.On the other hand, Figure 4 is a detailed block diagram of Figure 3, showing the water supply system (31, 35), emergency water supply system 33 and the steam generator (32, 36).
비상급수 시스템의 급수계통(31, 35)에는 각각 전동기구동펌프, 증기구동펌프가 개개의 배관과 밸브를 가지며 또한 서로 연결하는 배관연결점(42, 43)을 구비한다.The water supply system 31, 35 of the emergency water supply system has a pipe connection point 42, 43, in which the electric drive pump and the steam drive pump have respective pipes and valves, and are connected to each other.
또한, 두 개의 급수계통(31, 35)에서의 배관연결점(42, 43)을 다시 상호연결배관(44)으로 연결하여 비상급수계통(33)의 디젤구동펌프(40)의 밸브(41)와 연결하여 비상시에도 급수를 원활히 할 수 있도록 하는 것이다.In addition, the pipe connection points 42 and 43 of the two water supply systems 31 and 35 are connected to the interconnection pipe 44 again, so that the valve 41 of the diesel drive pump 40 of the emergency water supply system 33 and It is to connect the water supply smoothly even in an emergency.
한편, 격납건물 내부에 있는 증기발생기(32, 36)에는 각각 두개의 조절밸브(45, 46, 47, 48)를 구비하여 하나의 조절밸브가 작동되지 않더라도 비상급수를 원활하게 공급할 수 있도록 하는 것이다.Meanwhile, the steam generators 32 and 36 in the containment building are provided with two control valves 45, 46, 47, and 48, respectively, so that emergency water supply can be smoothly supplied even if one control valve is not operated. .
이상과 같이, 본 발명의 비상급수 시스템과 종래의 비상급수 시스템과의 차이점은 독립적으로만 가동되던 서브시스템을 서로 연결하는 것으로, 두 개 급수계통(31, 35)에 구비된 각각의 전동기구동펌프와 증기구동펌프의 배관을 배관연결점(42, 43)으로 상호 연결하여 비상급수의 공급을 다양하게 변화시켜서 사고에 대응할 수 있도록 하며, 각 서브시스템의 배관연결점(42, 43)을상호연결배관(44)에 연결하고 본 발명의 비상급수 계통(33)에 연결하여 비상급수의 공급을 안전하게 공급할 수 있도록 하는 것이다.As described above, the difference between the emergency water supply system of the present invention and the conventional emergency water supply system is to connect the subsystems that were operated independently independently, and each electric motor driven pump provided in the two water supply systems 31 and 35. And the piping of the steam drive pump to the pipe connection points (42, 43) to change the supply of emergency water to respond to the accident, and to connect the pipe connection points (42, 43) of each subsystem to the interconnection pipe ( 44) and connected to the emergency water supply system 33 of the present invention to safely supply the supply of emergency water.
또한, 증기발생기(32, 36)에는 각각 두개의 조절밸브(45~48)를 구비하여 하나의 조절밸브가 작동되지 않더라도 비상급수를 원활하게 공급할 수 있도록 하는 것이다.In addition, the steam generators 32 and 36 are provided with two control valves 45 to 48, respectively, so that emergency water supply can be smoothly supplied even though one control valve is not operated.
상술한 바와 같이, 본 발명은 원자력 발전소의 완전 전원 상실의 사고 시에는 원자력 발전소의 핵연료 손상 및 방사능 누출을 방지할 수 있도록 두개의 서브시스템 공용으로 디젤구동 펌프, 배관 및 수동밸브 등을 설치하여 비상급수를 안정적으로 공급하는 것이다.As described above, the present invention is to install a diesel driving pump, pipes and manual valves in common in two subsystems in order to prevent nuclear fuel damage and radiation leakage in the event of a complete power loss of the nuclear power plant emergency It is to supply water stably.
또한, 비상급수 기능의 다중성을 유지할 수 있도록 각 서브시스템 간의 배관연결점(42, 43)을 설치하고, 격납건물 내부에 위치한 증기발생기(32, 36)로 입력되는 비상급수를 조절할 수 있도록 하나의 증기발생기(32, 36)에 두개의 조절 밸브(45~48)을 구비하여 안전하게 비상급수를 제공하는 것이다.In addition, pipe connections (42, 43) between the subsystems are installed to maintain the multiplicity of emergency water supply function, and one steam to control the emergency water input to the steam generator (32, 36) located inside the containment building. Two control valves 45 to 48 are provided on the generators 32 and 36 to safely provide emergency water supply.
이상과 같이, 본 발명은 원자력 발전소에 운전중 급수상실, 증기발생기 튜브누설, 원자로 냉각제 상실사고 및 발전소 완전 전원 상실 사고, 밸브의 고착발생 시에 증기발생기로 비상급수를 계속적으로 안전하게 공급할 수 있어서 원자로 냉각재 계통을 냉각하고 원자로 및 연료손상 방지, 증기발생기를 통한 1차 측에서 2차 측으로 방사능 누출을 차단하여 원자력 발전소 비상급수 시스템의 안전성을 향상시키는 효과가 있다.As described above, the present invention can safely supply emergency water supply to the steam generator in the event of a water supply loss, steam generator tube leakage, reactor coolant loss, power plant complete power loss accident, or valve sticking during nuclear power plant operation. It cools the coolant system, prevents nuclear reactor and fuel damage, and blocks the leakage of radiation from the primary side to the secondary side through the steam generator, thereby improving the safety of the nuclear power plant emergency water supply system.
Claims (5)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| KR10-2001-0069865A KR100448876B1 (en) | 2001-11-09 | 2001-11-09 | Emergency feed water system in nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| KR10-2001-0069865A KR100448876B1 (en) | 2001-11-09 | 2001-11-09 | Emergency feed water system in nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| KR20030039062A KR20030039062A (en) | 2003-05-17 |
| KR100448876B1 true KR100448876B1 (en) | 2004-09-18 |
Family
ID=29568813
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| KR10-2001-0069865A KR100448876B1 (en) | 2001-11-09 | 2001-11-09 | Emergency feed water system in nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| KR (1) | KR100448876B1 (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101234570B1 (en) * | 2011-09-19 | 2013-02-19 | 한국원자력연구원 | Integrated type reactor capable of mitigating loss-of-coolant accident and its mitigation method |
| KR20160003006U (en) | 2015-02-24 | 2016-09-01 | 김흥일 | Cooling water circulation system for emergency generators |
| KR102572242B1 (en) * | 2020-12-30 | 2023-08-29 | 한국수력원자력 주식회사 | Coolant system of vapor generator and method for supplying coolant into vapor generator in the critical accident of the nuclear power plant |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4654190A (en) * | 1984-04-05 | 1987-03-31 | Westinghouse Electric Corp. | Emergency feedwater system for steam generators of a nuclear power plant |
| US4666662A (en) * | 1984-07-10 | 1987-05-19 | Westinghouse Electric Corp. | Steam generator recirculating system for a pressurized water nuclear reactor |
| KR20010076565A (en) * | 2000-01-26 | 2001-08-16 | 이종훈 | Passive Secondary Condensing System |
-
2001
- 2001-11-09 KR KR10-2001-0069865A patent/KR100448876B1/en active IP Right Grant
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4654190A (en) * | 1984-04-05 | 1987-03-31 | Westinghouse Electric Corp. | Emergency feedwater system for steam generators of a nuclear power plant |
| US4666662A (en) * | 1984-07-10 | 1987-05-19 | Westinghouse Electric Corp. | Steam generator recirculating system for a pressurized water nuclear reactor |
| KR20010076565A (en) * | 2000-01-26 | 2001-08-16 | 이종훈 | Passive Secondary Condensing System |
Also Published As
| Publication number | Publication date |
|---|---|
| KR20030039062A (en) | 2003-05-17 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US9312035B2 (en) | Semi-portable emergency cooling system for removing decay heat from a nuclear reactor | |
| US10008295B2 (en) | Emergency core cooling system and boiling water nuclear plant | |
| US5343507A (en) | Shutdown cooling system for operation during lapse of power | |
| US20130070887A1 (en) | Reactor adapted for mitigating loss-of-coolant accident and mitigation method thereof | |
| CN104508753A (en) | Defense in depth safety paradigm for nuclear reactor | |
| JP2008185572A (en) | Alternative cooling system for nuclear reactor and the like | |
| JPS60254000A (en) | Emergency feedwater facility for steam generator | |
| JPH056082B2 (en) | ||
| KR100448876B1 (en) | Emergency feed water system in nuclear power plant | |
| CN109801722B (en) | Heat exchange test method and system for plate heat exchanger of SEU (continuous emission unit) system of nuclear power plant | |
| KR102214119B1 (en) | Coolant recirculation system of nuclear power plant | |
| WO2022233141A1 (en) | Passive special safety system and water supply system for nuclear power plant | |
| CN110752046B (en) | Safety device, nuclear power plant system and safe operation method of nuclear power plant | |
| Conway et al. | Simplified safety and containment systems for the IRIS reactor | |
| JP2020012768A (en) | Reactor cooling system and operation method thereof | |
| JPS5913719B2 (en) | Residual heat removal system for fast breeder reactor | |
| CN215988120U (en) | Containment cooling water cooling device and passive containment cooling system | |
| RU2102800C1 (en) | Power plant | |
| JP7408470B2 (en) | Nuclear plant water supply equipment | |
| JP2001091684A (en) | Fuel pool cooling equipment | |
| CN209591543U (en) | A kind of Spent Fuel Pool cooling system | |
| JP3068288B2 (en) | Auxiliary cooling water system for nuclear power plants | |
| JPS5816479B2 (en) | Comprehensive reactor backup cooling system equipment | |
| Wu et al. | Study on Passive Pulse Cooling Method of Secondary Side in PWR Nuclear Power Plant | |
| CN116110622A (en) | Nuclear power plant equipment cooling water system |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A201 | Request for examination | ||
| N231 | Notification of change of applicant | ||
| E902 | Notification of reason for refusal | ||
| E701 | Decision to grant or registration of patent right | ||
| GRNT | Written decision to grant | ||
| FPAY | Annual fee payment |
Payment date: 20120903 Year of fee payment: 9 |
|
| FPAY | Annual fee payment |
Payment date: 20130902 Year of fee payment: 10 |
|
| FPAY | Annual fee payment |
Payment date: 20140901 Year of fee payment: 11 |
|
| FPAY | Annual fee payment |
Payment date: 20150903 Year of fee payment: 12 |
|
| FPAY | Annual fee payment |
Payment date: 20160902 Year of fee payment: 13 |
|
| FPAY | Annual fee payment |
Payment date: 20170831 Year of fee payment: 14 |
|
| FPAY | Annual fee payment |
Payment date: 20180905 Year of fee payment: 15 |
|
| FPAY | Annual fee payment |
Payment date: 20190904 Year of fee payment: 16 |