CN104854661A - Apparatus for replenishing coolant for passive auxiliary feedwater syatem of nuclear power plant - Google Patents
Apparatus for replenishing coolant for passive auxiliary feedwater syatem of nuclear power plant Download PDFInfo
- Publication number
- CN104854661A CN104854661A CN201280077615.3A CN201280077615A CN104854661A CN 104854661 A CN104854661 A CN 104854661A CN 201280077615 A CN201280077615 A CN 201280077615A CN 104854661 A CN104854661 A CN 104854661A
- Authority
- CN
- China
- Prior art keywords
- water
- passive
- drainer
- auxiliary feedwater
- steam
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
- G21C9/012—Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention relates to an apparatus for replenishing a coolant for a passive auxiliary feedwater system of a nuclear power plant, in which the passive auxiliary feedwater system additionally comprises a raw water system for supplying cold water to a passive condensation tank in case of an accident, the passive auxiliary feedwater system comprising the passive condensation tank comprising cold water and a condenser for supplying, to a nuclear reactor, steam from a steam generator condensed via heat exchange with the cold water. The present invention has the benefit of extending the operational hours of the passive auxiliary feedwater system by allowing a variety of coolant sources to be used.
Description
Technical field
The present invention relates to the filling device of the passive auxiliary feedwater system of nuclear power station, particularly relate to the filling device that the passive auxiliary feedwater system of nuclear power station of the former water of former water system can be provided to passive drainer.
Background technology
Nuclear power station utilizes the heat energy produced by the nuclear disintegration of fuel to produce steam to the Water transport heat through steam generator, and obtain the equipment of electric energy according to produced steam driven turbine and generator.
Nuclear power station needs to be equipped with preserves the reactor core of nuclear fuel and the nuclear reactor coolant system safe operation within design standards scope by making the heat energy produced in nuclear reactor pass to secondary side, thus maintain the safe condition of nuclear power station, and prevent the equipment of the diffusion of radiant material.
In order to realize safe operation, nuclear power station is equipped with the engineering safety device systems that can stop the operation in power station when having an accident safely.Engineering safety device systems comprises containment system (containmentsystem), emergency core cooling system (emergency core cooling system), passive auxiliary feedwater system (passive auxiliary feed water system).
As an example of described passive auxiliary feedwater system, Fig. 1 is the passive secondary side condenser system of light-water reactor disclosed in No. 10-1022164th, Korean granted patent, known with reference to Fig. 1, the passive secondary side condenser system of light-water reactor in the past discloses following formation: steam generator 10, and the heat by means of nuclear reactor produces steam, main steam pipe 11, is fed to turbine pusher side by the heat of described steam generator 10, main feed water pipe 12, steam through turbine is reclaimed by exchanging and the water of condensation with cooling water heat to steam generator 10, and be configured to when nuclear reactor interrupt run, block the steam supply to turbine pusher side, the condenser 20 of the steam by being flowed into by the steam supply pipe 13 of main steam pipe 11 branch and passive drainer 30 inside is made to carry out heat interchange and after being condensed into water, the hydration of condensation is flow to main feed water pipe 12 by the condensing hot air furnace pipe 14 exported by being connected to condenser 20, and condensing hot air furnace pipe 14 is provided with the adverse current preventing portion 40 of the adverse current of the water preventing from being condensed.
According to so passive secondary side condenser system, be not equipped with pump and so on special active devices and by natural convection mode by steam generator 10 produce steam after condenser 20 condensation, make the water of condensation turn back to steam generator 10 and cool nuclear reactor, there is overheated advantage accordingly that prevent nuclear reactor when nuclear power plant accident.
The chilled water being filled into described passive drainer 30 is 500,000 gallons, guarantees the refrigerating function having at least 8 hours.Produce this can the reason of restriction of cool time being, the chilled water in passive drainer 30 and condenser 20 heat interchange and its temperature rises gradually, the situation cannot being carried out condensation by condenser 20 is finally even occurred.
Therefore, for the accident of 8 hours, passive auxiliary feedwater system can run swimmingly by passive drainer 30 and perform cooling, but as the accident such as nearest Fukushima Nuclear Power Accident continue the long period time, there is the problem that passive auxiliary feedwater system cannot work.
Summary of the invention
Technical matters
For the object of the invention is to of solving the problem, the filling device of the passive auxiliary feedwater system of a kind of nuclear power station is provided, it adds the multiple water-filling source as water purification storage tank and former water storage tank on the passive drainer of passive auxiliary feedwater system, thus passive auxiliary feedwater system also can be made to work swimmingly when accident continues the long period.
Technical scheme
The filling device of the passive auxiliary feedwater system of nuclear power station of the present invention to achieve these goals relates to the filling device of the passive auxiliary feedwater system of nuclear power station, in the passive auxiliary feedwater system possessing passive drainer, the former water system of chilled water is provided to described passive drainer when being included in accident further, wherein, described passive drainer comprises condensate water and carries out condensation for the steam of the steam generator with this condensate water heat interchange and be supplied to the condenser of nuclear reactor.
Technique effect
The present invention is configured to the water be stored in the water purification storage tank of former water system and former water storage tank to add in passive drainer, has the effect of the working time that can extend passive auxiliary feedwater system thus.
Accompanying drawing explanation
Fig. 1 is the pie graph of the passive auxiliary feedwater system of existing nuclear power station.
Fig. 2 is the pie graph of the filling device of the passive auxiliary feedwater system of nuclear power station according to an embodiment of the invention.
Fig. 3 is the pie graph of the filling device of the passive auxiliary feedwater system of nuclear power station according to another embodiment of the present invention.
To the explanation of the symbol of major part in accompanying drawing
100: passive-type secondary side condenser system 110: steam generator
111: main steam pipe 112,112-1,112-2: main feed water pipe
112a: saving nozzle of water 112b: lower (operating) water nozzle
113: steam supply pipe 114: condensing hot air furnace pipe
120: condenser 130: condensate draining
200: former water system 210: water purification storage tank
220: former water storage tank 300: waste water tank
400: desalted water storage tank
Embodiment
Below, be described with reference to the filling device of accompanying drawing for the passive auxiliary feedwater system of nuclear power station of the preferred embodiment of the present invention.
Fig. 2 is the pie graph of the filling device of the passive auxiliary feedwater system of nuclear power station according to the preferred embodiment of the invention.
With reference to Fig. 2, the filling device of the passive auxiliary feedwater system of nuclear power station according to the present invention possesses by carrying out heat interchange with the cold-producing medium being circulated in nuclear reactor and produces steam generator 110 primary side of steam in accommodating container, the secondary side being provided to the steam generator 110 of the outside of accommodating container is connected with the main steam pipe 111 steam resulting from steam generator 110 being supplied to turbine (not shown) side, and the steam be equipped with through turbine is condensed by carrying out heat interchange with chilled water, thus be recovered to main feed water pipe (112) 112-1 of steam generator 110, 112-2.Reference numeral W represents the outer wall of accommodating container.
Described main steam pipe 111 is provided with main steam stop valve from the steam to the supply of turbine pusher side V1, V2, V3, the V4 of the flowing for controlling, thus be configured to, when nuclear reactor normally runs, described main steam stop valve V1, V2, V3, V4 are made steam supply to turbine pusher side by opening, and when nuclear reactor outage, described main steam stop valve V1, V2, V3, V4 are closed and cut off the steam supply to turbine pusher side.
Described main feed water pipe (112) 112-1,112-2 are branched to the arm 112-1 being connected to the saving nozzle of water 112a being provided to steam generator 110 bottom and the arm 112-2 being connected to the lower (operating) water nozzle 112b being provided to steam generator 110 top, and described main feed water pipe (112) 112-1,112-2 are provided with non-return valve V6, V7, V9 of main feedwater stop valve V5, V8 of the flowing for controlling the water reclaimed to steam generator 110 side from turbine and the counterflow-preventing for main feedwater.
Have condenser 120 in the outer setting of described accommodating container, this condenser 120 carries out condensation for the steam resulting from steam generator 110 when nuclear reactor is out of service and makes condensate water turn back to steam generator 110.Described condenser 120 is arranged with the state within the passive drainer 130 being immersed in inside and being filled with chilled water, and the steam through condenser 120 is condensed into water by exchanging with the cooling water heat be filled in passive drainer 130.The exhaust valve V13 for non-condensing gas being discharged to passive drainer 130 is provided with in the side of described condenser 120.
There is steam supply pipe 113 in described main steam pipe 111 top set, and the other end of described steam supply pipe 113 is connected to the entrance side of condenser 120.Described steam supply pipe 113 is provided with steam stop valve V10, V11.Described steam stop valve V10, V11 are in pent state when nuclear reactor normally runs and the steam cut off to condenser 120 flows into, and opened when nuclear reactor interrupt run, the steam produced on steam generator 110 is thus by flowing into condenser 120 from the steam supply pipe 113 of main steam pipe 111 branch.And, described steam supply pipe 113 is provided with draining valve V12, accordingly when the part in the water vapour comprised in steam is because discharging by draining valve V12 when temperature and pressure change is condensed.
The condensing hot air furnace pipe 114 water be condensed through condenser 120 being supplied to main feed water pipe 112 side is connected with between the outlet of described condenser 120 and main feed water pipe 112.Described condensing hot air furnace pipe 114 is connected in parallel to respectively water supply control valve V14, V15 and non-return valve V16, V17 as counterflow-preventing unit.Therefore, when one of them in one of them in water supply control valve V14, V15 or non-return valve V16, V17 breaks down, condensate water is supplied swimmingly by the remaining valve be connected in parallel.
According to above-mentioned formation, nuclear power station be in very accident and the outage of nuclear reactor time, the steam produced in steam generator 110 is provided to condenser 120 side by the steam supply pipe 113 from main steam pipe 111 branch by natural convection, and fall because of the weight of self at the water that condenser 120 is condensed, and be provided to steam generator 120 through condensing hot air furnace pipe 114 by main feed water pipe 112, thus nuclear reactor is cooled.
Such effect does not rely on the special active elements of pump and so on, and by means of utilizing the passive device of the spontaneous phenomenon of natural convection and gravity and so on to supply water to steam generator 110.
Under above-mentioned effect, when passive auxiliary feedwater system continues to play a role, by the heat interchange with described condenser 120, its water temperature of chilled water of described passive drainer 130 rises, and the work of passive auxiliary feedwater system becomes and has some setbacks.
As previously mentioned, the chilled water of described passive drainer 130 can play the cooling effect of about 8 hours, after during having exceeded this, pump 211,221 is used the water purification be stored in the water purification storage tank 210 of former water system 200 and former water storage tank 220 and Yuan Shui to be fed in described passive drainer 130 respectively.
So, when the water purification of former water system 200 and former water are fed to passive drainer 130 respectively, the cooling water temperature in passive drainer 130 can be reduced, the working time smoothly of passive auxiliary feedwater system can be extended.
Fig. 3 is the pie graph of the filling device of the passive auxiliary feedwater system of nuclear power station according to another embodiment of the present invention.
With reference to Fig. 3, the filling device of the passive auxiliary feedwater system of nuclear power station comprises further in the structure illustrated with reference to Fig. 2 according to another embodiment of the present invention provides the waste water tank 300 of the waste water system of chilled water and the desalted water storage tank 400 of supplementing water desalination system respectively to described passive drainer 130 and forms.
The waste water being stored in the waste water tank 300 of described waste water system and the desalted water being stored in desalted water storage tank 400 both can be supplied effectively directly in described passive drainer 130, also after can being fed to described water purification storage tank 210 in advance, then be fed in passive drainer 130.
So, the present invention can use various water-filling source by chilled(cooling) water supply (CWS) in passive drainer, can extend the working time smoothly of passive auxiliary feedwater system accordingly.
The present invention is not limited to above-described embodiment, and within the scope not departing from technology main idea of the present invention, can carry out multiple amendment, distortion and implementing, this is apparent for the technician in the technical field of the invention with usual knowledge.
Claims (3)
1. the filling device of the passive auxiliary feedwater system of nuclear power station, in the passive auxiliary feedwater system possessing passive drainer, the former water system of chilled water is provided to described passive drainer when being included in accident further, wherein, described passive drainer comprises condensate water and carries out condensation for the steam of the steam generator with this condensate water heat interchange and be supplied to the condenser of nuclear reactor.
2. the filling device of the passive auxiliary feedwater system of nuclear power station according to claim 1, is characterized in that, described former water system comprises:
Water purification storage tank, stores water purification;
Former water storage tank, stores former water;
Pump, supplies described passive drainer by the former water extraction of the water purification of described water purification storage tank or described former water storage tank.
3. the filling device of the passive auxiliary feedwater system of nuclear power station according to claim 2, it is characterized in that, also comprise and provide the waste water tank of the waste water system of chilled water and the desalted water storage tank of supplementing water desalination system to described passive drainer, the water stored in described waste water tank and desalted water storage tank is directly supplied to described passive drainer or is supplied to described passive drainer by described water purification storage tank.
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| KR1020120113779A KR20140047452A (en) | 2012-10-12 | 2012-10-12 | Coolant replenishment apparatus for passive auxiliary feedwater system of nuclear power plant |
| KR10-2012-0113779 | 2012-10-12 | ||
| PCT/KR2012/008493 WO2014058090A1 (en) | 2012-10-12 | 2012-10-17 | Apparatus for replenishing coolant for passive auxiliary feedwater syatem of nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104854661A true CN104854661A (en) | 2015-08-19 |
| CN104854661B CN104854661B (en) | 2017-03-29 |
Family
ID=50477546
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201280077615.3A Active CN104854661B (en) | 2012-10-12 | 2012-10-17 | The filling device of the passive auxiliary feedwater system of nuclear power station |
Country Status (4)
| Country | Link |
|---|---|
| JP (1) | JP2015534649A (en) |
| KR (1) | KR20140047452A (en) |
| CN (1) | CN104854661B (en) |
| WO (1) | WO2014058090A1 (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101498697B1 (en) * | 2014-08-28 | 2015-03-05 | 김영선 | Nuclear power generation system |
| KR101921406B1 (en) * | 2017-01-02 | 2018-11-22 | 한국수력원자력 주식회사 | Nuclear reactor system for SMR having improved cooling reliability |
| KR102267104B1 (en) * | 2019-04-18 | 2021-06-21 | 한국수력원자력 주식회사 | Cooling system for external wall of reactor vessel and cooling method of external wall of reactor vessel using the same |
| KR102455236B1 (en) | 2020-07-23 | 2022-10-18 | 한국수력원자력 주식회사 | A cooling system using unuseful water of passive auxiliary feedwater system |
| KR102550140B1 (en) * | 2021-03-02 | 2023-06-30 | 한국전력기술 주식회사 | Passive auxiliary feedwater supply system of nuclear power plant using overcooling prevention apparatus |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4687626A (en) * | 1985-01-18 | 1987-08-18 | Tong Long S | Passive safety device for emergency steam dump and heat removal for steam generators in nuclear power reactors |
| JPH08248166A (en) * | 1995-03-13 | 1996-09-27 | Toshiba Corp | Reactor container cooling facility |
| KR20010076565A (en) * | 2000-01-26 | 2001-08-16 | 이종훈 | Passive Secondary Condensing System |
| CN101719386A (en) * | 2009-12-21 | 2010-06-02 | 肖宏才 | Entire passive shutdown safe cooling device of advanced pressurized water reactor nuclear power plant and operation program thereof |
| CN102163469A (en) * | 2011-02-14 | 2011-08-24 | 中国核电工程有限公司 | Nuclear power station non-active engineering safety system |
| KR101160771B1 (en) * | 2011-01-03 | 2012-06-28 | 한국수력원자력 주식회사 | Condensation-tank optimization of advanced passive auxiliary feed-water system for pressurized water reactor |
Family Cites Families (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2606469B2 (en) * | 1976-02-18 | 1977-12-22 | Kraftwerk Union AG, 4330 Mülheim | EMERGENCY FEED SYSTEM FOR COOLING NUCLEAR REACTOR PLANTS |
| FR2584228B1 (en) * | 1985-07-01 | 1987-12-24 | Framatome Sa | EMERGENCY COOLING DEVICE WITH INTRINSIC SAFETY OF A PRESSURE WATER NUCLEAR REACTOR. |
| JPS6244692A (en) * | 1985-08-22 | 1987-02-26 | 株式会社東芝 | Decay heat removing device for nuclear reactor |
| JPS63275992A (en) * | 1987-05-07 | 1988-11-14 | Toshiba Corp | Cooling apparatus for nuclear reactor |
| JP2000180582A (en) * | 1998-12-11 | 2000-06-30 | Toshiba Corp | Reactor power plant |
| KR100363574B1 (en) * | 2000-01-26 | 2002-12-05 | 한국수력원자력 주식회사 | Method for controling of passive secondary condensing system in nuclear power plant |
| KR100419194B1 (en) * | 2000-11-13 | 2004-02-19 | 한국전력공사 | Emergency Core Cooling System Consists of Reactor Safeguard Vessel and Accumulator |
| DE10328773B3 (en) * | 2003-06-25 | 2005-02-17 | Framatome Anp Gmbh | Nuclear facility |
| KR100856501B1 (en) * | 2007-04-06 | 2008-09-04 | 한국원자력연구원 | The safety features of an integral reactor using a passive spray system |
-
2012
- 2012-10-12 KR KR1020120113779A patent/KR20140047452A/en not_active Application Discontinuation
- 2012-10-17 WO PCT/KR2012/008493 patent/WO2014058090A1/en active Application Filing
- 2012-10-17 CN CN201280077615.3A patent/CN104854661B/en active Active
- 2012-10-17 JP JP2015536664A patent/JP2015534649A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4687626A (en) * | 1985-01-18 | 1987-08-18 | Tong Long S | Passive safety device for emergency steam dump and heat removal for steam generators in nuclear power reactors |
| JPH08248166A (en) * | 1995-03-13 | 1996-09-27 | Toshiba Corp | Reactor container cooling facility |
| KR20010076565A (en) * | 2000-01-26 | 2001-08-16 | 이종훈 | Passive Secondary Condensing System |
| CN101719386A (en) * | 2009-12-21 | 2010-06-02 | 肖宏才 | Entire passive shutdown safe cooling device of advanced pressurized water reactor nuclear power plant and operation program thereof |
| KR101160771B1 (en) * | 2011-01-03 | 2012-06-28 | 한국수력원자력 주식회사 | Condensation-tank optimization of advanced passive auxiliary feed-water system for pressurized water reactor |
| CN102163469A (en) * | 2011-02-14 | 2011-08-24 | 中国核电工程有限公司 | Nuclear power station non-active engineering safety system |
Also Published As
| Publication number | Publication date |
|---|---|
| KR20140047452A (en) | 2014-04-22 |
| CN104854661B (en) | 2017-03-29 |
| WO2014058090A1 (en) | 2014-04-17 |
| JP2015534649A (en) | 2015-12-03 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN105810256B (en) | A kind of nuclear power station passive residual heat removal system | |
| KR101463440B1 (en) | Passive safety system and nuclear power plant having the same | |
| US20180350472A1 (en) | Passive safe cooling system | |
| CN105810257B (en) | A kind of passive nuclear power station pressure release condensation heat exchange system | |
| KR101242746B1 (en) | Integrated passive safety system outside containment for nuclear power plants | |
| CN103617815A (en) | Passive residual heat exhausting system of pressurized water reactor nuclear power plant | |
| CN104361913A (en) | Secondary side passive waste heat removal system | |
| CN104854661A (en) | Apparatus for replenishing coolant for passive auxiliary feedwater syatem of nuclear power plant | |
| CN107403650B (en) | Secondary side passive waste heat discharging system of offshore floating nuclear power station | |
| JP2013057655A (en) | Driven-type cooling system in nuclear power plant | |
| CN104508753A (en) | Defense in depth safety paradigm for nuclear reactor | |
| CN109841288B (en) | Be used for carbon dioxide cooling reactor waste heat discharge system | |
| CN104205239A (en) | System for discharging residual power of pressurized water nuclear reactor | |
| KR101892550B1 (en) | Nuclear power plant having intermediate heat sink cooling device | |
| KR101505475B1 (en) | Passive containment cooling system and nuclear power plant having the same | |
| JP2013228281A (en) | Emergency reactor core cooling system and nuclear reactor facilities provided with the same | |
| CN104737236A (en) | Apparatus for replenishing coolant for passive auxiliary feedwater syatem of nuclear power plant | |
| KR101502393B1 (en) | Passive safety system and nuclear reactor having the same | |
| RU96283U1 (en) | PASSIVE HEAT REMOVAL SYSTEM THROUGH A STEAM GENERATOR | |
| CN108447570B (en) | Marine reactor and secondary side passive waste heat discharging system thereof | |
| KR20200091247A (en) | Coolant recirculation system of nuclear power plant | |
| KR20140040518A (en) | Passive secondary condensation system for light water reactor equipped with water supplying system to steam generator in case of emergency against station blackout or defunctionalization of passive auxiliary feedwater system in nuclear power plant | |
| CN207489488U (en) | A kind of pressurized water reactor peculiar to vessel and its primary side non-kinetic residual heat removal system | |
| KR101695363B1 (en) | Passive safety system and nuclear power plant having the same | |
| CN204242602U (en) | Secondary side passive residual heat guiding system |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| EXSB | Decision made by sipo to initiate substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |