CN104505130B - A kind of passive emergency feedwater supply system of nuclear power station - Google Patents
A kind of passive emergency feedwater supply system of nuclear power station Download PDFInfo
- Publication number
- CN104505130B CN104505130B CN201410658879.9A CN201410658879A CN104505130B CN 104505130 B CN104505130 B CN 104505130B CN 201410658879 A CN201410658879 A CN 201410658879A CN 104505130 B CN104505130 B CN 104505130B
- Authority
- CN
- China
- Prior art keywords
- steam
- emergency feedwater
- supply system
- jet pump
- 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
-
- 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
- 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
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of passive emergency feedwater supply system of nuclear power station, the characteristics of from relying on electronic, steam-operating or Diesel engine pump offer emergency feedwater in traditional nuclear power station emergency feedwater supply system, is different, the present invention uses steam jet pump, caused steam is used as driving source using in reactor steam generator, when losing electrification outside main feedwater and forfeiture factory, passive emergency feedwater supply system is fetched water from emergency feedwater source, steam generator is transported to after steam jet pump boosts, and sensible heat and the decay heat of primary Ioops are outwards taken away by main steam line.Steam jet pump be it is a kind of do not consume mechanical energy directly, the supercharging equipment of movement-less part, there is the advantages of more simple and reliable than the supercharging equipment of tradition machinery.The system takes away decay heat and the sensible heat of primary Ioops using passive equipment, realizes the cooling of primary Ioops, has good feasibility and reliability.
Description
Technical field
The present invention relates to nuclear power station safety full guard system, more particularly to a kind of passive emergency feedwater supply system.
Background technology
The emergency feedwater supply system of conventional pressurized water heap uses as the back-up system of main feed system in main feedwater failure.
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 will reaction
Heap is cooled to the state that residual heat removal system can put into operation.Emergency feedwater supply system category engineered safeguards features, given losing master
Under the transient state of water or secondary side steam line break, 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, the system are provided with AP1000 presurized water reactors
Conventional island is arranged in, in main feedwater and forfeiture normal communication electricity event is lost, is absorbed water from condensate tank to steam generator
Feedwater is provided, so as to realize the depth defense function of discharge reactor coolant loop heat, prevents passive safety system from moving
Make.In above process, the heat of reactor coolant loop passes to secondary coolant circuit system, secondary circuit system by steam generator
System is by taking heat out of to turbine bypass system or air discharge.
Chinese utility model patent (application number 201220447271.8, notification number CN202855318U) discloses a kind of non-
Active startup cooling system, it can be under accident conditions, due to main feed pump tripping operation and steam generator secondary side pressure
The factors such as change influence, and break the pressure balance of reason density lock holding, so as to realize the startup of cooling system, without existing skill
The emergency power supply of art starts, and improves the reliability, security and economy of system.Chinese utility model patent (application number
201220540653.5, notification number CN202948736U) be a kind of Heat Discharging System of Chinese, it is in station blackout operating mode
Under, reactor core decay heat is exported, ensures the safety of reactor, reduces the requirement to arrangement space, while reduce direct and anti-
The pipeline for answering reactor coolant system to connect, reduces the probability of pipe breakage, improves security.Above-mentioned two utility model
Essence is the heat using the condensation discharge primary Ioops of steam.
In existing presurized water reactor emergency feedwater supply system, drive device includes electrodynamic pump, Diesel engine pump and pneumatic pump, not
In same nuclear power station, using different types of combination of drive means, diversity is realized.The characteristics of above-mentioned three kinds of drive devices be with
Power supply or diesel engine realize feedwater conveying as driving source, and with rotating machinery.If can design it is a kind of have passive characteristic and
There is no the emergency feedwater supply system of moving component, the safety system for making nuclear power station is more safe and reliable.
The content of the invention
In view of above mentioned problem existing for prior art, it is an object of the invention to provide a kind of nuclear power station it is passive meet an urgent need to
Water system, it is not necessary to the power drives and Diesel Driven of traditional nuclear power plant, and there is no rotating machinery and moving component, system letter
It is single reliable.
Decay heat after reactor shutdown is taken away by the cooling water being passed through from main feed water pipe road under normal circumstances, cooling water
It is changed into steam at the steam generator of reactor to discharge from main steam line again, condensing is entered by the by-passing valve on pipeline
Device, or air is discharged into by main steam safety valve.
In order to realize the purpose of the present invention, the technical solution adopted by the present invention is a kind of passive emergency feedwater system of nuclear power station
System, including steam jet pump component and emergency feedwater source, steaming described in the activated vapor discharged using the steam generator of reactor
Vapour jet pump assembly, the steam generation of the reactor is transported to after the emergency feedwater entered from the emergency feedwater source stream is boosted
In device, the caused steam main steam line discharge through the steam generator again, so as to take away the damp and hot of primary Ioops and decay
Heat.
Further, the passive emergency feedwater supply system of the nuclear power station can also include with lower component：Steam inlet pipe line, water inlet
Pipeline and water outlet pipeline；Described steam inlet pipe line one end is connected with the main steam line of the steam generator, the other end with it is described
The steam inlet of steam jet pump component is connected；Described back with water inlet line one end is connected with the emergency feedwater source, the other end and institute
The water inlet for stating steam jet pump component is connected；Described water outlet pipeline one end and the delivery port phase of the steam jet pump component
Even, the other end is connected with the steam generator；Emergency feedwater, which is provided with, on wherein described steam inlet pipe line enters vapour isolating valve, it is described
Emergency feedwater isolating valve is provided with water outlet pipeline.
Under normal operation, the passive emergency feedwater supply system is in stand-by state, the emergency feedwater enter vapour every
Closed from valve and the emergency feedwater isolating valve, the cooling water temperature that the reactor is passed through by main feed water pipe road, cooling water warp
Steam is produced after crossing the steam generator, the steam is discharged from the main steam line, is entered by the by-passing valve on pipeline
Enter condenser, or air is discharged into by main steam safety valve；When occurring to lose main water supply accident, emergency feedwater enters vapour isolating valve
To be opened with emergency feedwater isolating valve, some vapor in main steam line enters steam jet pump component through the steam inlet pipe line,
Mixed with the emergency feedwater flowed into from the back with water inlet line and enter steam generator through the water outlet pipeline after boosting.
Further, the steam jet pump component can be single-stage jet pump or multi-stage jet pump group；Such as figure
Shown in 3 to Fig. 5, the steam jet pump component can be single-stage jet pump, two-stage or plural serial stage jet pump, or two-stage or more
Level jet pump in parallel.
Further, the water outlet pipeline of the passive emergency feedwater supply system of the nuclear power station can be separately provided directly connect
Enter the pipeline of the steam generator, the startup in the main feed water pipe road or the reactor of the steam generator can also be passed through
Feedwater piping, it is connected by the main feed water pipe road or the startup feedwater piping with the steam generator.
Preferably, it is additionally provided with emergency feedwater in the back with water inlet line and enters water isolation valve.
Preferably, emergency feedwater is additionally provided with the steam inlet pipe line and enters steam control valve, is also set up on the water outlet pipeline
There is emergency feedwater regulating valve.
Further, it is steam generator that the emergency feedwater, which enters steam control valve and the control signal of emergency feedwater regulating valve,
Interior liquid level and pressure.
Preferably, emergency feedwater is additionally provided with the steam inlet pipe line and enters vapour check-valves, is also set up on the water outlet pipeline
There is emergency feedwater check-valves.
Preferably, the passive emergency feedwater supply system of the nuclear power station also includes reflux pipeline and experiment pipeline, the backflow
Pipeline one end is connected with the emergency feedwater source, and the other end is connected with the delivery port of the steam jet pump component；The experiment
Pipeline one end is connected with auxiliary steam outlet, and the other end is connected with the steam inlet of the steam jet pump component；It is wherein described
Emergency feedwater backflow isolating valve is provided with reflux pipeline, auxiliary steam isolating valve is provided with the experiment pipeline.Described time
Flow tube line and experiment pipeline can realize the routine test of emergency feedwater supply system.During routine test, emergency feedwater is entered into vapour isolating valve
Closed with emergency feedwater isolating valve, auxiliary steam isolating valve and emergency feedwater backflow isolating valve are opened, by auxiliary steam as steaming
The driving source of vapour jet pump, checking steam jet pump meet performance requirement.
Preferably, emergency feedwater backflow orifice plate is additionally provided with the reflux pipeline.
Preferably, it is additionally provided with auxiliary steam regulating valve on the experiment pipeline.
Preferably, emergency feedwater backflow check-valves is additionally provided with the reflux pipeline, is additionally provided with experiment pipeline auxiliary
Help steam check-valves.
The passive emergency feedwater supply system of nuclear power station provided by the invention may be arranged to：One steam generator configures one
Passive emergency feedwater supply system, can also be configured as needed, for example, the configuration of steam generator it is multiple it is passive should
Anxious water supply system, or more steam generators configure a passive emergency feedwater supply system.
System provided by the invention can apply to safety-related system, can also be applied to perform depth defense function
Non-safety-related system.
The invention has the advantages that：
The present invention proposes a kind of passive emergency feedwater supply system design of new nuclear power station, and the design should with traditional nuclear power station
The characteristics of electronic, steam-operating or Diesel engine pump offer emergency feedwater are relied in anxious water supply system is different, using steam jet pump, with anti-
Answer caused steam in heap steam generator passive to answer when losing electrification outside main feedwater and forfeiture factory as driving source
Anxious water supply system is fetched water from emergency feedwater source, steam generator is transported to after steam jet pump boosts, and pass through main steam pipe
Outwards take away sensible heat and the decay heat of primary Ioops in road.Steam jet pump be it is a kind of do not consume mechanical energy directly, movement-less part
Supercharging equipment, there is the advantages of more simple and reliable than the supercharging equipment of tradition machinery.The system utilizes passive equipment belt
Decay heat and the sensible heat of primary Ioops are walked, realizes the cooling of primary Ioops, there is good feasibility and reliability.
Design, concrete structure and the caused technique effect of the present invention are described further below with reference to accompanying drawing, with
It is fully understood from the purpose of the present invention, feature and effect.
Brief description of the drawings
Fig. 1 is the general flow chart of the passive emergency feedwater supply system of nuclear power station in embodiment 1；
Fig. 2 is the general flow chart of the passive emergency feedwater supply system of nuclear power station in embodiment 2；
Fig. 3 is the schematic diagram of single-stage vapor jet pump；
Fig. 4 is the schematic diagram of two-stage or plural serial stage steam jet pump；
Fig. 5 is the schematic diagram of two-stage or plural parallel stage steam jet pump.
Embodiment
Embodiment 1
As shown in figure 1, in the present embodiment, under normal circumstances, reactor is dropped by the cooling water being passed through from main feed water pipe road 2
Temperature, cooling water are changed into steam at the steam generator 1 of reactor and discharged again from main steam line 3, are done work through steam turbine laggard
Enter condenser (not shown), main steam safety valve 4, atmospheric rilief valve 5 and main steaming are additionally provided with the main steam line 3
Vapour isolating valve 6, main feed check (valve) 7, main feed-regulating valve 8 and main feed water isolating valve 9 are provided with the main feed water pipe road 2.
Passive emergency feedwater supply system is arranged on outside the containment of reactor, including steam jet pump component 15, meet an urgent need to
Water tank 26, long-term water source 27, steam inlet pipe line, back with water inlet line, water outlet pipeline, reflux pipeline and experiment pipeline.The steam inlet pipe line
One end is connected with main steam line 3, and the other end is connected with the steam inlet of the steam jet pump component 15；The back with water inlet line
One end is connected with the emergency feedwater case 26 and long-term water source 27, the water inlet phase of the other end and the steam jet pump component 15
Even；Described water outlet pipeline one end is connected with the delivery port of the steam jet pump component 15, the other end and the steam generator 1
It is joined directly together；Described reflux pipeline one end is connected with the emergency feedwater case 26, the other end and the steam jet pump component 15
Delivery port be connected；Described experiment pipeline one end is connected with auxiliary steam outlet 22, the other end and the steam jet pump component
15 steam inlet is connected.
Be provided with that emergency feedwater enters steam control valve 10, emergency feedwater enters vapour isolating valve 11 on the steam inlet pipe line and meet an urgent need to
Water enters vapour check-valves 12, is provided with that emergency feedwater enters water isolation valve 13 and emergency feedwater enters Water Check Valve in the back with water inlet line
14, emergency feedwater check-valves 16, emergency feedwater regulating valve 17 and emergency feedwater isolating valve 18, institute are provided with the water outlet pipeline
State and emergency feedwater backflow orifice plate 19, emergency feedwater backflow check-valves 20 and emergency feedwater backflow isolating valve are provided with reflux pipeline
21, described test is provided with auxiliary steam regulating valve 23, auxiliary steam isolating valve 24 and auxiliary steam check-valves 25 on pipeline.
Under normal operation, passive emergency feedwater supply system is in stand-by state, enters vapour isolating valve 11 by emergency feedwater
It is isolated with steam generator 1 and main steam line 3 with emergency feedwater isolating valve 18, will be aided in by auxiliary steam isolating valve 24
Steam is isolated with emergency feedwater supply system.
When occurring to lose main water supply accident, emergency feedwater enters vapour isolating valve 11 and emergency feedwater isolating valve 18 is opened, portion
The steam divided in main steam line 3 enters steam jet pump 15 through emergency feedwater steam inlet pipe line, is answered with what is flowed into from back with water inlet line
Enter steam generator 1 through water outlet pipeline after anxious feedwater mixing boosting.Feedwater absorbs the heat of primary Ioops in a vapor generator
It is transformed into steam, most steam are discharged into condenser by side, or are arranged by atmospheric rilief valve 3 (main steam safety valve 4)
Enter air, take away decay heat and the sensible heat of primary Ioops, driving source of the fraction steam as jet pump 15.In emergency feedwater case 26
Equipped with the water for meeting cooling requirement, also enough feedwater can be provided by long-term water source 27 to meet extra cooling required.On
Decay heat and sensible heat that process takes away primary Ioops using passive equipment are stated, realizes the cooling of primary Ioops, there is well feasible
Property and reliability.
Liquid level and pressure in steam generator 1 enter steam control valve 10 and emergency feedwater regulating valve 17 as emergency feedwater
Control signal.
The routine test of emergency feedwater supply system is realized by experiment pipeline and reflux pipeline.During routine test, confirmation meet an urgent need to
Water enters vapour isolating valve 11 and emergency feedwater isolating valve 18 is closed, and opens auxiliary steam isolating valve 24 and emergency feedwater backflow isolating valve
21, by driving source of the auxiliary steam 22 as jet pump 15, checking jet pump 15 meets performance requirement.
The connection of former components is only the exemplary illustration of the present invention and non-limitative illustration or other connections
Mode.
Embodiment 2
As shown in Fig. 2 the present embodiment and the structure of embodiment 1 are essentially identical, difference is the emergency feedwater supply system
Water outlet pipeline be passed through in the main feed water pipe road 2, be connected by main feed water pipe road 2 with the steam generator, be now not required to
Emergency feedwater regulating valve is set in addition, and the main feed-regulating valve 8 in main feed water pipe road 2 can double as adjusting for emergency feedwater
Valve.
Preferred embodiment of the invention described in detail above.It should be appreciated that one of ordinary skill in the art without
Creative work can is needed to make many modifications and variations according to the design of the present invention.Therefore, all technologies in the art
Personnel are available by logical analysis, reasoning, or a limited experiment on the basis of existing technology under this invention's idea
Technical scheme, all should be in the protection domain being defined in the patent claims.
Claims (8)
- A kind of 1. passive emergency feedwater supply system of nuclear power station, it is characterised in that including steam jet pump component and emergency feedwater source, Steam jet pump component described in the activated vapor discharged using the steam generator of reactor, will be entered from the emergency feedwater source stream Emergency feedwater boosting after be transported in the steam generator of the reactor, caused steam is again through the steam generator Main steam line is discharged, so as to take away the damp and hot and decay heat of primary Ioops；Also include steam inlet pipe line, back with water inlet line and water outlet pipeline；Described steam inlet pipe line one end and the main steaming of the steam generator Steam pipe road is connected, and the other end is connected with the steam inlet of the steam jet pump component；Answered with described described back with water inlet line one end Anxious water-supply source and long-term water source are connected, and the other end is connected with the water inlet of the steam jet pump component；The water outlet pipeline one End is connected with the delivery port of the steam jet pump component, and the other end is connected with the steam generator；Wherein described steam inlet pipe Emergency feedwater is provided with line and enters vapour isolating valve, emergency feedwater isolating valve is provided with the water outlet pipeline；When occurring to lose main water supply accident, the emergency feedwater enters vapour isolating valve and the emergency feedwater isolating valve is opened, portion The steam divided in main steam line enters the steam jet pump component through the steam inlet pipe line, with being flowed into from the back with water inlet line Emergency feedwater mixing boosting after through the water outlet pipeline enter the steam generator；Also include reflux pipeline and experiment pipeline；Described reflux pipeline one end is connected with the emergency feedwater source, the other end and institute The delivery port for stating steam jet pump component is connected；Experiment pipeline one end and the auxiliary steam, which export, to be connected, the other end with it is described The steam inlet of steam jet pump component is connected；Emergency feedwater backflow isolating valve is provided with wherein described reflux pipeline, it is described Auxiliary steam isolating valve is provided with experiment pipeline.
- 2. the passive emergency feedwater supply system of nuclear power station as claimed in claim 1, it is characterised in that the steam jet pump component It is single-stage jet pump or multi-stage jet pump group.
- 3. the passive emergency feedwater supply system of nuclear power station as claimed in claim 1, it is characterised in that the water outlet pipeline directly connects Enter the steam generator, or be passed through the main feed water pipe road of the steam generator or the startup feedwater piping of the reactor, It is connected by the main feed water pipe road or the startup feedwater piping with the steam generator.
- 4. the passive emergency feedwater supply system of nuclear power station as claimed in claim 1, it is characterised in that also set on the steam inlet pipe line It is equipped with emergency feedwater and enters steam control valve, emergency feedwater regulating valve is additionally provided with the water outlet pipeline.
- 5. the passive emergency feedwater supply system of nuclear power station as claimed in claim 4, it is characterised in that the emergency feedwater enters vapour tune The control signal for saving valve and emergency feedwater regulating valve is the liquid level and pressure in steam generator.
- 6. the passive emergency feedwater supply system of nuclear power station as claimed in claim 1, it is characterised in that also set on the reflux pipeline Emergency feedwater backflow orifice plate is equipped with, auxiliary steam regulating valve is additionally provided with the experiment pipeline.
- 7. the passive emergency feedwater supply system of nuclear power station as claimed in claim 1 a, it is characterised in that steam generator A passive emergency feedwater supply system is configured, or a steam generator configures multiple passive emergency feedwater supply systems, or The more steam generators configure a passive emergency feedwater supply system.
- 8. the passive emergency feedwater supply system of nuclear power station as claimed in claim 1 is in safety-related systems and performs depth defense work( Application in the non-safety-related system of energy.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410658879.9A CN104505130B (en) | 2014-11-18 | 2014-11-18 | A kind of passive emergency feedwater supply system of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410658879.9A CN104505130B (en) | 2014-11-18 | 2014-11-18 | A kind of passive emergency feedwater supply system of nuclear power station |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104505130A CN104505130A (en) | 2015-04-08 |
| CN104505130B true CN104505130B (en) | 2017-11-10 |
Family
ID=52946871
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410658879.9A Active CN104505130B (en) | 2014-11-18 | 2014-11-18 | A kind of passive emergency feedwater supply system of nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104505130B (en) |
Families Citing this family (12)
| 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 |
| CN104952495A (en) * | 2015-06-26 | 2015-09-30 | 上海核工程研究设计院 | Secondary side residual heat removal system for twin-reactor nuclear power plant |
| CN104966535A (en) * | 2015-06-26 | 2015-10-07 | 上海核工程研究设计院 | Sea water desalination and residual heat removal dual-purpose system of floating nuclear power plant |
| CN104952496A (en) * | 2015-06-26 | 2015-09-30 | 上海核工程研究设计院 | Emergent water supply system of floating nuclear power station |
| CN105070325A (en) * | 2015-08-14 | 2015-11-18 | 上海核工程研究设计院 | Nuclear power station safety injection system adopting steam-jet pump |
| CN105070326A (en) * | 2015-08-18 | 2015-11-18 | 上海核工程研究设计院 | Primary loop feeding and discharging system for nuclear power plant |
| CN105401611A (en) * | 2015-11-18 | 2016-03-16 | 中国核电工程有限公司 | System and method for supplying water to radioactive regions of nuclear chemical engineering plant |
| CN105427903A (en) * | 2015-12-11 | 2016-03-23 | 哈尔滨工程大学 | Recycling safety injection system adopting gas-liquid booster pump and applied to nuclear power plant |
| CN108087093A (en) * | 2017-12-31 | 2018-05-29 | 沪东重机有限公司 | The cooling water off-line equipment of nuclear power diesel emergency generating set |
| CN109767852B (en) * | 2019-02-22 | 2024-06-04 | 西安热工研究院有限公司 | Two-loop safety system for reactor emergency shutdown and working method thereof |
| CN113421667A (en) * | 2021-05-10 | 2021-09-21 | 中广核研究院有限公司 | Reactor primary loop spraying system |
| CN114234173B (en) * | 2021-12-17 | 2022-09-23 | 华能山东石岛湾核电有限公司 | Nuclear power station steam generator cooling system |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5108695A (en) * | 1991-02-25 | 1992-04-28 | Westinghouse Electric Corp. | Ventilating system for an emergency feedwater enclosure in a nuclear power plant |
| FR2742253B1 (en) * | 1995-12-12 | 1998-03-06 | Framatome Sa | DEVICE FOR SPRAYING A PRESSURIZER OF A NUCLEAR PRESSURE WATER REACTOR |
| JP4834349B2 (en) * | 2005-08-18 | 2011-12-14 | 株式会社東芝 | Reactor containment cooling equipment |
| JP5578630B2 (en) * | 2008-12-03 | 2014-08-27 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | Chemical cleaning method and chemical cleaning system for performing steam injection |
| CN101800085B (en) * | 2009-02-11 | 2012-06-27 | 中国核电工程有限公司 | Auxiliary water supply system used for nuclear power station single reactor and actuating safety function |
| CN204229849U (en) * | 2014-11-18 | 2015-03-25 | 上海核工程研究设计院 | The non-active emergency feedwater supply system of a kind of nuclear power station |
-
2014
- 2014-11-18 CN CN201410658879.9A patent/CN104505130B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN104505130A (en) | 2015-04-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104505130B (en) | A kind of passive emergency feedwater supply system of nuclear power station | |
| CN204229849U (en) | The non-active emergency feedwater supply system of a kind of nuclear power station | |
| US9460818B2 (en) | Low pressure reactor safety systems and methods | |
| CN104575636B (en) | A kind of low discharge backflow and current limiting control apparatus | |
| CN105070329A (en) | Nuclear power station secondary side passive residual heat removal system | |
| CN101800085B (en) | Auxiliary water supply system used for nuclear power station single reactor and actuating safety function | |
| CN106887265B (en) | The start and stop shut-down system of one bulb bed modular high temperature gas cooled reactor | |
| CN105070326A (en) | Primary loop feeding and discharging system for nuclear power plant | |
| CN113808764B (en) | Method and system for guiding out residual heat of reactor core in containment | |
| CN113860415B (en) | Deoxygenation method, water supply system and catalytic deoxygenation device for emergency water supply tank of nuclear power plant | |
| US8528588B2 (en) | Safety valve drive system | |
| CN104952495A (en) | Secondary side residual heat removal system for twin-reactor nuclear power plant | |
| CN203366766U (en) | Secondary side discharge system for alleviating vapor generator's heat-transfer pipe cracking accidents | |
| US20110249784A1 (en) | Driving system of relief safety valve | |
| CN205038971U (en) | Long -term residual heat removal system of nuclear power station secondary side | |
| KR102214119B1 (en) | Coolant recirculation system of nuclear power plant | |
| CN104934080A (en) | Main water supply system of double-reactor nuclear power station | |
| CN204760046U (en) | Active emergency feedwater system of long -term non - of floating nuclear power plant | |
| CN113555137B (en) | Safe injection system of nuclear power station | |
| CN105070327A (en) | Nuclear power station secondary side long-term waste heat removal system | |
| CN104934079A (en) | Long-term passive emergency water supply system for floating nuclear power plant | |
| CN104952496A (en) | Emergent water supply system of floating nuclear power station | |
| JP2017120226A (en) | Cooling installation and nuclear power plant | |
| CN112309598A (en) | Overpressure protection system of nuclear power station and nuclear power station | |
| CN204732169U (en) | A kind of emergency feedwater supply system of floating nuclear power plant |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder | ||
| 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 |