CN204760046U - Active emergency feedwater system of long -term non - of floating nuclear power plant - Google Patents
Active emergency feedwater system of long -term non - of floating nuclear power plant Download PDFInfo
- Publication number
- CN204760046U CN204760046U CN201520453872.3U CN201520453872U CN204760046U CN 204760046 U CN204760046 U CN 204760046U CN 201520453872 U CN201520453872 U CN 201520453872U CN 204760046 U CN204760046 U CN 204760046U
- Authority
- CN
- China
- Prior art keywords
- pipeline
- emergency feedwater
- steam
- emergency
- feedwater
- 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.)
- Active
Links
Classifications
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The utility model relates to an active emergency feedwater system of long -term non - of floating nuclear power plant, include steam generator and be connected the main steam pipe line with steam generator, steam generator still connects the emergency feedwater pipeline, drive steam pipeline connection main steam pipe line and steam extraction pipeline, be provided with the drive steam control valve on the drive vapor line, steam extraction pipeline connection is on the drive vapor line, emergency feedwater import pipeline is connected to the other end of emergency feedwater pipeline, the emergency feedwater case is connected to the emergency feedwater import pipeline other end, the drive vapor line is provided with steam jet pump with the junction of emergency feedwater pipeline, be provided with emergency feedwater isolating valve and emergency feedwater check valve on the emergency feedwater pipeline between steam jet pump and the steam generator. The utility model discloses avoid adopting rotating machinery electronic or diesel driven, and adopt steam jet pump to realize providing emergency feedwater for steam generator to emergency feedwater case entry add with the communicating pipe of sea water, realize cooling off for a long time.
Description
Technical field
The utility model relates to nuclear power plant system, particularly relates to a kind of long-term non-active emergency feedwater supply system of floating nuclear power plant.
Background technology
The emergency feedwater supply system of conventional pressurized water heap is as back-up system use when main feedwater was lost efficacy of main feed system.Under the breakdown operating mode of power station, emergency feedwater supply system is used for maintaining power station hot shutdown operating mode with time enough, and reactor is cooled to the state that residual heat removal system can put into operation.Emergency feedwater supply system is used to prevent reactor core from damaging, and discharges reactor core decay heat, until residual heat removal system puts into operation.Non-security relevant startup water supply system is provided with in third generation presurized water reactor, this system layout is at conventional island, in the main feedwater of forfeiture and forfeiture normal communication electricity event, feedwater is provided to steam generator from the water suction of condensate water tank, thus realize the depth defense function of discharging reactor coolant loop heat, prevent passive safety system action.In above process, the heat of reactor coolant loop passes to secondary coolant circuit system by steam generator, and secondary coolant circuit system is by taking heat out of to turbine bypass system or airborne release.
In existing presurized water reactor emergency feedwater supply system, mainly through power supply or diesel engine as drive source, and fetch water to steam generator conveying feedwater from emergency feedwater case, to take away reactor core decay heat with rotating machinery.The capacity of emergency feedwater case is limited, for floating nuclear power plant, seawater is inexhaustible, use not to the utmost.Floating nuclear power plant can using seawater as natural ultimate heat sink; if one can be designed, and there is long-term refrigerating function; and there is the emergency feedwater supply system of non-energy dynamic characteristic, make heat enter seawater, by making, the safety system of floating nuclear power plant is more safe and reliable.
Utility model content
The utility model is exactly that overcome problems of the prior art, the utility model provides a kind of long-term non-active emergency feedwater supply system of floating nuclear power plant to satisfy the demands in order to solve the problem.
To achieve these goals, the technical solution of the utility model is as follows:
A kind of long-term non-active emergency feedwater supply system of floating nuclear power plant, comprise steam generator and be connected main steam pipe with steam generator, it is characterized in that, described steam generator also connects emergency feedwater pipeline, also comprise and drive vapour line and steam discharge pipeline, described driving vapour line connects main steam pipe and steam discharge pipeline, described main steam pipe is also provided with main steam isolation valve, the junction of described driving vapour line and main steam pipe is arranged between main steam isolation valve and steam generator, described driving vapour line is provided with driving steam regulating valve, steam discharge pipeline is connected to and drives on vapour line, steam discharge pipeline is provided with steam discharge pipeline isolation valve, the other end of described emergency feedwater pipeline connects emergency feedwater inlet line, the emergency feedwater inlet line other end connects emergency feedwater case, emergency feedwater inlet line is provided with emergency feedwater import isolation valve, the junction of described driving vapour line and emergency feedwater pipeline is provided with steam jet pump, emergency feedwater pipeline between steam jet pump and steam generator is provided with emergency feedwater isolation valve and emergency feedwater non-return valve.
The long-term non-active emergency feedwater supply system of above-mentioned a kind of floating nuclear power plant, it is characterized in that, described emergency feedwater pipeline is also connected with sea intake pipeline, described sea intake pipeline is provided with sea intake pipeline isolation valve, the sea intake of described sea intake pipeline is provided with sea intake pipeline filter screen.
The long-term non-active emergency feedwater supply system of above-mentioned a kind of floating nuclear power plant, it is characterized in that, also comprise Natural Circulation pipeline, one section of described Natural Circulation pipeline is connected on the emergency feedwater pipeline between emergency feedwater non-return valve and emergency feedwater isolation valve, the sea intake end of described Natural Circulation pipeline is provided with Natural Circulation pipeline filter screen, described Natural Circulation pipeline is also provided with Natural Circulation pipeline isolation valve.
The long-term non-active emergency feedwater supply system of above-mentioned a kind of floating nuclear power plant, is characterized in that, the endpiece of described steam discharge pipeline is provided with porous air diffuser.
The beneficial effects of the utility model are: the long-term non-active emergency feedwater supply system of the floating nuclear power plant that the utility model provides, avoid adopting electronic or diesel-driven rotating machinery, and adopt steam jet pump to be embodied as steam generator to provide emergency feedwater, and set up the connecting pipe with seawater at emergency feedwater tank inlet, realize cooling for a long time.Set up Natural Circulation pipeline simultaneously, utilized non-active mechanism that reactor core decay heat is imported seawater, there is safe and reliable advantage.
Accompanying drawing explanation
Fig. 1 is structural representation of the present utility model.
Embodiment
The technological means realized to make the utility model, creation characteristic, reaching object and effect is easy to understand, below in conjunction with concrete diagram, setting forth the utility model further.
Referring to Fig. 1, a kind of long-term non-active emergency feedwater supply system of floating nuclear power plant, comprise steam generator 1 and be connected main steam pipe 2 with steam generator 1, steam generator 1 also connects emergency feedwater pipeline 12, also comprise and drive vapour line 4 and steam discharge pipeline 5, vapour line 4 is driven to connect main steam pipe 2 and steam discharge pipeline 5, main steam pipe 2 is also provided with main steam isolation valve 3, the junction of vapour line 4 and main steam pipe 2 is driven to be arranged between main steam isolation valve 3 and steam generator 1, drive on vapour line 4 and be provided with driving steam regulating valve 8, steam discharge pipeline 5 is connected to and drives on vapour line 4, steam discharge pipeline 5 is provided with steam discharge pipeline isolation valve 6, the other end of emergency feedwater pipeline 12 connects emergency feedwater inlet line 15, emergency feedwater inlet line 15 other end connects emergency feedwater case 13, emergency feedwater inlet line 15 is provided with emergency feedwater import isolation valve 14, drive vapour line 4 that the junction of emergency feedwater pipeline 12 is provided with steam jet pump 9, emergency feedwater pipeline 12 between steam jet pump 9 and steam generator 1 is provided with emergency feedwater isolation valve 10 and emergency feedwater non-return valve 11.
Emergency feedwater pipeline 12 is also connected with sea intake pipeline 17, sea intake pipeline 17 is provided with sea intake pipeline isolation valve 18, and the sea intake of sea intake pipeline 17 is provided with sea intake pipeline filter screen 16.
Also comprise Natural Circulation pipeline 20, one end of Natural Circulation pipeline 20 is connected on the emergency feedwater pipeline 12 between emergency feedwater non-return valve 11 and emergency feedwater isolation valve 10, the sea intake end of Natural Circulation pipeline 20 is provided with Natural Circulation pipeline filter screen 19, Natural Circulation pipeline 20 is also provided with Natural Circulation pipeline isolation valve 21.
In one of them preferred implementation of the present utility model, the endpiece of steam discharge pipeline 5 is provided with porous air diffuser 7.
The long-term non-active emergency feedwater supply system of floating nuclear power plant is arranged between the containment of reactor and floating nuclear power plant dividing plate, when power station is run, emergency feedwater supply system is in stand-by state, emergency feedwater supply system and steam generator 1 and main steam pipe 2 is isolated by steam discharge pipeline isolation valve 6, emergency feedwater isolation valve 10, emergency feedwater non-return valve 11 and Natural Circulation pipeline isolation valve 21.And by steam discharge pipeline isolation valve 6, driving steam regulating valve 8, sea intake pipeline isolation valve 18 and Natural Circulation pipeline isolation valve 21, emergency feedwater supply system and seawater are isolated.
When occurring to lose main feedwater event, opening and driving steam regulating valve 8, emergency feedwater isolation valve 10 and steam discharge pipeline isolation valve 6, and closing main steam isolation valve 3.Emergency feedwater import isolation valve 14 is normally open valves, steam is driven to enter steam jet pump 9 through driving vapour line 4, emergency feedwater simultaneously in emergency feedwater case 13 enters steam jet pump 9 under gravity, steam and feedwater enter steam generator 1 after mixing boosting in steam jet pump 9, after feedwater is transformed into steam, enter seawater by steam discharge pipeline 5 and porous air diffuser 7, reactor core decay heat is taken out of.
When the emergency feedwater in emergency feedwater case 13 is finished, open sea intake pipeline isolation valve 18, close emergency feedwater import isolation valve 14.Seawater enters steam jet pump 9 through sea intake pipeline filter screen 16 and sea intake pipeline 17 under gravity, enter steam generator 1 after boosting with steam, after being transformed into steam, enter seawater by steam discharge pipeline 5 and porous air diffuser 7, reactor core decay heat is taken out of, realizes cooling for a long time.
If along with the reduction of steam generator 1 pressure and the minimizing of quantity of steam, steam is driven to be not enough to maintain the operation of steam jet pump 9, keep main steam isolation valve 3, drive steam regulating valve 8, emergency feedwater isolation valve 10 and Natural Circulation pipeline isolation valve 21 are in closed condition, open steam discharge pipeline isolation valve 6, by steam discharge pipeline 5 and porous air diffuser 7, steam generator 1 pressure is reduced to enough low, now open Natural Circulation pipeline isolation valve 21, seawater injects steam generator 1 through Natural Circulation pipeline filter screen 19 and Natural Circulation pipeline 20 under gravity, open type Natural Circulation is formed with steam discharge pipeline 5, reactor core decay heat is imported seawater, realize long-term cooling.
The beneficial effects of the utility model are: the long-term non-active emergency feedwater supply system of the floating nuclear power plant that the utility model provides, avoid adopting electronic or diesel-driven rotating machinery, and adopt steam jet pump to be embodied as steam generator to provide emergency feedwater, and set up the connecting pipe with seawater at emergency feedwater tank inlet, realize cooling for a long time.Set up Natural Circulation pipeline simultaneously, utilized non-active mechanism that reactor core decay heat is imported seawater, there is safe and reliable advantage.
More than show and describe ultimate principle of the present utility model, principal character and advantage of the present utility model.The technician of the industry should understand; the utility model is not restricted to the described embodiments; what describe in above-described embodiment and instructions just illustrates principle of the present utility model; under the prerequisite not departing from the utility model spirit and scope, the utility model also has various changes and modifications, and these changes and improvements all fall within the scope of claimed the utility model.The claimed scope of the utility model is defined by appending claims and equivalent thereof.
Claims (4)
1. the long-term non-active emergency feedwater supply system of a floating nuclear power plant, comprise steam generator and be connected main steam pipe with steam generator, it is characterized in that, described steam generator also connects emergency feedwater pipeline, also comprise and drive vapour line and steam discharge pipeline, described driving vapour line connects main steam pipe and steam discharge pipeline, described main steam pipe is also provided with main steam isolation valve, the junction of described driving vapour line and main steam pipe is arranged between main steam isolation valve and steam generator, described driving vapour line is provided with driving steam regulating valve, steam discharge pipeline is connected to and drives on vapour line, steam discharge pipeline is provided with steam discharge pipeline isolation valve, the other end of described emergency feedwater pipeline connects emergency feedwater inlet line, the emergency feedwater inlet line other end connects emergency feedwater case, emergency feedwater inlet line is provided with emergency feedwater import isolation valve, the junction of described driving vapour line and emergency feedwater pipeline is provided with steam jet pump, emergency feedwater pipeline between steam jet pump and steam generator is provided with emergency feedwater isolation valve and emergency feedwater non-return valve.
2. the long-term non-active emergency feedwater supply system of a kind of floating nuclear power plant according to claim 1, it is characterized in that, described emergency feedwater pipeline is also connected with sea intake pipeline, described sea intake pipeline is provided with sea intake pipeline isolation valve, the sea intake of described sea intake pipeline is provided with sea intake pipeline filter screen.
3. the long-term non-active emergency feedwater supply system of a kind of floating nuclear power plant according to claim 2, it is characterized in that, also comprise Natural Circulation pipeline, one section of described Natural Circulation pipeline is connected on the emergency feedwater pipeline between emergency feedwater non-return valve and emergency feedwater isolation valve, the sea intake end of described Natural Circulation pipeline is provided with Natural Circulation pipeline filter screen, described Natural Circulation pipeline is also provided with Natural Circulation pipeline isolation valve.
4. a kind of long-term non-active emergency feedwater supply system of floating nuclear power plant according to claim 1 or 3, is characterized in that, the endpiece of described steam discharge pipeline is provided with porous air diffuser.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201520453872.3U CN204760046U (en) | 2015-06-26 | 2015-06-26 | Active emergency feedwater system of long -term non - of floating nuclear power plant |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201520453872.3U CN204760046U (en) | 2015-06-26 | 2015-06-26 | Active emergency feedwater system of long -term non - of floating nuclear power plant |
Publications (1)
Publication Number | Publication Date |
---|---|
CN204760046U true CN204760046U (en) | 2015-11-11 |
Family
ID=54474728
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201520453872.3U Active CN204760046U (en) | 2015-06-26 | 2015-06-26 | Active emergency feedwater system of long -term non - of floating nuclear power plant |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN204760046U (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104934079A (en) * | 2015-06-26 | 2015-09-23 | 上海核工程研究设计院 | Long-term passive emergency water supply system for floating nuclear power plant |
WO2022237216A1 (en) * | 2021-05-10 | 2022-11-17 | 中广核研究院有限公司 | Reactor primary circuit spray system |
-
2015
- 2015-06-26 CN CN201520453872.3U patent/CN204760046U/en active Active
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104934079A (en) * | 2015-06-26 | 2015-09-23 | 上海核工程研究设计院 | Long-term passive emergency water supply system for floating nuclear power plant |
WO2022237216A1 (en) * | 2021-05-10 | 2022-11-17 | 中广核研究院有限公司 | Reactor primary circuit spray system |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN204229849U (en) | The non-active emergency feedwater supply system of a kind of nuclear power station | |
CN1197092C (en) | BWR nuclear power generator | |
CN104505130A (en) | Nuclear power station passive emergency water supply system | |
US9460818B2 (en) | Low pressure reactor safety systems and methods | |
CN105070329A (en) | Nuclear power station secondary side passive residual heat removal system | |
CN104508753A (en) | Defense in depth safety paradigm for nuclear reactor | |
CN105070326A (en) | Primary loop feeding and discharging system for nuclear power plant | |
CN108831573A (en) | A kind of nuclear power station secondary side passive residual heat removal security system | |
CN204760046U (en) | Active emergency feedwater system of long -term non - of floating nuclear power plant | |
CN107013271B (en) | Comprehensive utilization system for natural gas power generation complementary energy | |
CN205064358U (en) | Urgent bearing seal injected water feeding mechanism of nuclear main pump | |
CN104934079A (en) | Long-term passive emergency water supply system for floating nuclear power plant | |
CN204514104U (en) | A kind of thermal power plant evacuation system for steam condenser energy saver | |
CN204732169U (en) | A kind of emergency feedwater supply system of floating nuclear power plant | |
CN104952496A (en) | Emergent water supply system of floating nuclear power station | |
CN205722809U (en) | A kind of spray cooling system for Nuclear Power Station's Exhausted Fuels pond | |
CN205038971U (en) | Long -term residual heat removal system of nuclear power station secondary side | |
CN110726132B (en) | Method and system for supplying water to steam generator of nuclear power station under low-power working condition | |
CN205038972U (en) | Active residual heat removal system of nuclear power station secondary side non - | |
CN105070327A (en) | Nuclear power station secondary side long-term waste heat removal system | |
WO2022252359A1 (en) | Novel automatic depressurizing system and method for nuclear power plant | |
CN204530859U (en) | Nuclear power plant's emergency feedwater supply system flow control device | |
CN202484973U (en) | Water supply system of steam generator | |
CN204760044U (en) | Two core power station secondary side waste heat discharge systems | |
CN105179301B (en) | Core main pump is with passive urgent injection water supply system |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C14 | Grant of patent or utility model | ||
GR01 | Patent grant | ||
CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
|
CP01 | Change in the name or title of a patent holder |