CN104681111A - Auxiliary water supply flow segmented regulation control method - Google Patents
Auxiliary water supply flow segmented regulation control method Download PDFInfo
- Publication number
- CN104681111A CN104681111A CN201510009327.XA CN201510009327A CN104681111A CN 104681111 A CN104681111 A CN 104681111A CN 201510009327 A CN201510009327 A CN 201510009327A CN 104681111 A CN104681111 A CN 104681111A
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- CN
- China
- Prior art keywords
- auxiliary feedwater
- valve
- feedwater flow
- steam generator
- water supply
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- 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.)
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/086—Pressurised water reactors
-
- 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
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K5/00—Plants characterised by use of means for storing steam in an alkali to increase steam pressure, e.g. of Honigmann or Koenemann type
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
- F22D5/00—Controlling water feed or water level; Automatic water feeding or water-level regulators
- F22D5/26—Automatic feed-control systems
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
-
- 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
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Emergency Management (AREA)
- Business, Economics & Management (AREA)
- Mechanical Engineering (AREA)
- Thermal Sciences (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Safety Devices In Control Systems (AREA)
- Control Of Turbines (AREA)
Abstract
The invention belongs to a nuclear power station automatic control technology, and particularly relates to an auxiliary water supply flow segmented regulation control method. The method is characterized in that after an auxiliary water supply system puts into operation, an electromagnetic valve of an auxiliary water supply flow regulating valve is electrified, and the regulating valve automatically enters a regulating mode; a control system judges the liquid level height of a steam generator, and the opening degree of the auxiliary water supply flow regulating valve is regulated in a segmented way according to the height liquid level setting value, so that the liquid level of the steam generator is maintained in a certain range; after the regulating mode quits the operation, the electromagnetic valve of the auxiliary water supply flow regulating value is de-energized, and the regulating valve is recovered to the full open position. The auxiliary water supply flow segmented regulation control method has the advantages that the influence of human intervention factors on the operation stability of a nuclear power station is reduced, the potential risk of the auxiliary water supply control of the nuclear power station is avoided, and the effectiveness of the auxiliary water supply system and the safety level of the power station operation are improved.
Description
Technical field
The invention belongs to nuclear power station automatic control technology, be specifically related to the control method that a kind of auxiliary feedwater flow that can be used for matching with the liquid level in steam generator is sectional-regulated.
Background technology
Auxiliary feedwater system is the ad hoc system of important safety in advanced pressurized water reactor nuclear power plant.It is when reactor has an accident, to steam generator moisturizing, to discharge residual heat of nuclear core.This system disposition has 6 auxiliary feedwater flow control valves, wherein A row and each 3 of B row.
In nuclear power station design in the past, there is features in auxiliary feedwater system:
The fault position of auxiliary feedwater flow control valve is standard-sized sheet position.Each auxiliary feedwater flow control valve is furnished with the solenoid valve of being arranged by A respectively of two series connection and B row Power supply and control, any row solenoid valve dead electricity all can make auxiliary feedwater flow control valve standard-sized sheet, only have when A row and B row solenoid valve are simultaneously charged, valve is in shaping modes.After auxiliary feedwater starts, valve according to individual to the observation of power station operational factor with after judging, must be placed in shaping modes, manual adjustments auxiliary feedwater flow regulation valve opening, control auxiliary feedwater flow by operator.The working strength of this designing requirement operator is large, adds the contingency occurrence probability of people because causing simultaneously.In addition, lose the control signal of A row or B row or the electrical source of power of any solenoid valve, all will cause 6 variable valve standard-sized sheets, and valve cannot enter shaping modes, operator cannot in master-control room by-pass valve control aperture, auxiliary feedwater system carries out moisturizing with maximum refill flow to SG, and too much auxiliary feedwater may cause steam generator spill-over.
In the design of ACP1000 nuclear power station, for the security consideration of requirements at the higher level, propose the requirement not allowing manual intervention after accident in a period of time.
For meeting above-mentioned requirements, improve the security of auxiliary feedwater further, the human intervention degree after reduction accident, need to take corresponding innovative approach, automatically regulated the aperture of auxiliary feedwater flow control valve by segmentation, guarantee that SG liquid level maintains in the scope of functional requirement, spill-over does not occur.
Summary of the invention
The object of the invention is the requirement for nuclear plant safety design, provide a kind of according to steam generator liquid level, the control method of sectional-regulated auxiliary feedwater flow.
Technical scheme of the present invention is as follows: the control method that a kind of auxiliary feedwater flow is sectional-regulated, the method is after auxiliary feedwater system puts into operation, make the solenoid valve of auxiliary feedwater flow control valve charged by automatic interlock signal, variable valve enters shaping modes automatically; The height of liquid level of control system to steam generator judges, according to the aperture of the sectional-regulated auxiliary feedwater flow control valve of two position setting value, makes the liquid level of steam generator maintain in certain scope; After shaping modes is out of service, the solenoid valve dead electricity of auxiliary feedwater flow control valve, variable valve returns to standard-sized sheet position.
Further, the control method that auxiliary feedwater flow as above is sectional-regulated, wherein, each auxiliary feedwater flow control valve only configures a solenoid valve, carries out Power supply and control by auxiliary feedwater flow control valve column; Steering logic and the auxiliary feedwater pipeline of auxiliary feedwater flow control valve match, and realize Redundancy Design, after any row power supply or control signal lost efficacy, can not affect the normal operation of other row auxiliary feedwaters.
Further, the control method that auxiliary feedwater flow as above is sectional-regulated, wherein, the level gauging signal redundancy configuration of steam generator, meets the requirement of single failure; Signal, respectively by 4 protection group collections, carries out after threshold value compares, getting through 4 the aperture that 2 voting logics judge control valve with steam generator two position setting value; Sectional-regulated steering logic, in the processor process of redundant configuration, is guaranteed redundancy and the validity of signal further, is met the requirement of security function.
Further again, the control method that auxiliary feedwater flow as above segmentation regulates automatically, wherein, except automatic segmentation regulates, control system is also designed with manual adjustments function, ensure that manual intervention if desired.
Further, the control method that auxiliary feedwater flow as above is sectional-regulated, wherein, after auxiliary feedwater flow control valve enters sectional-regulated pattern, when the liquid level of steam generator reaches two position setting value, the regulating stage by stage of control system to auxiliary feedwater flow control valve is as follows:
When the liquid level of steam generator reaches high setting value, the aperture of variable valve is adjusted to 5 ~ 40%;
When the liquid level of steam generator reaches low setting value, the aperture of variable valve is adjusted to 80 ~ 100%;
When steam generator liquid level is between two position setting value, controller keeps previous moment to export, and the aperture of variable valve is constant;
Auxiliary feedwater variable valve will be in sectional-regulated pattern always, until there is reset signal, exit shaping modes, and variable valve returns to standard-sized sheet position.
Beneficial effect of the present invention is as follows: every platform auxiliary feedwater flow control valve configures a solenoid valve, to control or power supply is single row accordingly, solves the problem that any row fault all can cause other row valves standard-sized sheet simultaneously.Within the design that automatic segmentation regulates can guarantee that steam generator liquid level maintains the scope of functional requirement, both meet the requirement not needing manual intervention within a certain period of time, in turn ensure that enough auxiliary feedwater flows, to discharge residual heat of nuclear core.The enforcement of the method, solves the potential risk of nuclear power station auxiliary feedwater function in the past, decreases the impact of human intervention factor on power station operation stability, improves the validity of auxiliary feedwater system and the security level of power station operation.
Accompanying drawing explanation
Fig. 1 is the implementation schematic diagram of the sectional-regulated control of auxiliary feedwater flow of the present invention.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail.
After auxiliary feedwater system puts into operation, for guaranteeing that steam generator in certain hour (SG) spill-over does not occur, also can ensure enough confluents simultaneously, after auxiliary feedwater pump startup, control system according to the height of liquid level of steam generator, the valve opening of Discrete control auxiliary feedwater flow control valve.
Every platform auxiliary feedwater flow control valve configures 1 solenoid valve, solenoid valve belongs to a part for auxiliary feedwater flow control valve, be positioned in the gas circuit of auxiliary feedwater flow control valve, corresponding control or power supply are single row, and any row fault can not affect the normal work of other row valves.
The level gauging signal redundancy configuration of steam generator, meets the requirement of single failure.Signal, respectively by 4 protection group collections, carries out after threshold value compares, getting through 4 the aperture that 2 voting logics judge control valve with SG height of liquid level setting value.
Embodiment
As shown in Figure 1, the auxiliary feedwater of every platform steam generator completes after being converged by female pipeline by the auxiliary feedwater flow that A arranges and B arranges.This accompanying drawing only for the Discrete control of A row auxiliary feedwater flow control valve, summarizes, and the control strategy of B row is identical.
The controller of system receives 4 signals: steam generator liquid level height signal and liquid level low signal; Hand automatic switching signal (for providing the function of hand/automatic switchover); Manual/auto control station signal (when being in manual mode, the opening degree instruction of exportable valve).
After auxiliary feedwater system puts into operation, rest-set flip-flop receives the instruction that puts into operation, and the solenoid valve of flow control valve is charged, and valve enters sectional-regulated pattern, and the result that controller compares according to steam generator level threshold exports opening degree instruction signal.The level measurement of steam generator gathers at protection group IP-IVP, and carries out threshold value (XU) with the two position setting value of setting and compare.When liquid level reaches high setting value, it is 1 that high threshold compares output, the threshold value comparative result of multiple Measurement channel is after 4 select 2 voting logics judgements, voting result sends into controller, controlling electropneumatic transducer (EP) makes valve opening be 5% ~ 40%, and in the present embodiment, the aperture of valve is adjusted to 10%.Because valve opening diminishes, feedwater flow reduces, and steam generator liquid level declines; When liquid level reaches low setting value, it is 1 that Low threshold compares output, and threshold value comparative result, after 4 select 2 logic voting judgements, sends into controller, controlling electropneumatic transducer (EP) makes valve opening be 80% ~ 100%, and in the present embodiment, the aperture of valve is adjusted to 100%.When steam generator liquid level is between two position setting value, controller keeps previous moment to export, and the aperture of variable valve is constant.By that analogy, steam generator Liquid level within the scope of the liquid level of functional requirement.Until there is the reset signal of solenoid valve shaping modes, rest-set flip-flop receives reset instruction, and variable valve exits shaping modes, returns to standard-sized sheet position.
Be provided with rest-set flip-flop in figure, the startup command introducing auxiliary feed water pump input as the set end of rest-set flip-flop, and S output terminal feeding solenoid valve, to ensure that, when auxiliary feedwater starts, solenoid valve can be charged for a long time, and valve is in adjustable state.
The automatic no-harass switch function of hand is provided with in this programme.For ensureing manual intervention if desired, controller, except automatic control function, can also accept manual control signal.When automatically cutting manual, manual ringing regulates from current aperture, can not produce disturbance.Manual switchover signal and rest-set flip-flop output signal mutually or send into solenoid valve, charged adjustable to guarantee the valve under manual mode.
The realization of interrelated logic relation can be inner at Digitizing And Control Unit DCS, and come by Logical Configuration, also can utilize the principle of programming, the program module special in DCS indoor design realizes.
The present invention is from the angle of Control System Design, provide auxiliary feedwater put into operation after the specific design scheme of auxiliary feedwater flow control system, this programme considers auxiliary feedwater system simultaneously and comes into operation and do not come into operation two stages, is applicable to any operating mode that nuclear power station runs.Automatic segmentation in scheme regulates the flow automatic regulation function can guaranteeing auxiliary feedwater system, ensure that the regulatory function without auxiliary feedwater flow in personnel's intervention situation after accident, and its built-in manual adjustments, is also that manual intervention if desired provides means.
Obviously, those skilled in the art can carry out various change and modification to the present invention and not depart from the spirit and scope of the present invention.Like this, if belong within the scope of the claims in the present invention and equivalent technology thereof to these amendments of the present invention and modification, then the present invention is also intended to comprise these change and modification.
Claims (5)
1. the control method that auxiliary feedwater flow is sectional-regulated, is characterized in that: the method is after auxiliary feedwater system puts into operation, and make the solenoid valve of auxiliary feedwater flow control valve charged by automatic interlock signal, variable valve enters shaping modes automatically; The height of liquid level of control system to steam generator judges, according to the aperture of the sectional-regulated auxiliary feedwater flow control valve of two position setting value, makes the liquid level of steam generator maintain in certain scope; After shaping modes is out of service, the solenoid valve dead electricity of auxiliary feedwater flow control valve, variable valve returns to standard-sized sheet position.
2. the control method that auxiliary feedwater flow as claimed in claim 1 is sectional-regulated, is characterized in that: each auxiliary feedwater flow control valve only configures a solenoid valve, carries out Power supply and control by auxiliary feedwater flow control valve column; Steering logic and the auxiliary feedwater pipeline of auxiliary feedwater flow control valve match, and realize Redundancy Design, after any row power supply or control signal lost efficacy, can not affect the normal operation of other row auxiliary feedwaters.
3. the control method that auxiliary feedwater flow as claimed in claim 1 is sectional-regulated, is characterized in that: the level gauging signal redundancy configuration of steam generator, meets the requirement of single failure; Signal, respectively by 4 protection group collections, carries out after threshold value compares, getting through 4 the aperture that 2 voting logics judge control valve with steam generator two position setting value; Sectional-regulated steering logic, in the processor process of redundant configuration, is guaranteed redundancy and the validity of signal further, is met the requirement of security function.
4. the control method that auxiliary feedwater flow as claimed in claim 3 is sectional-regulated, is characterized in that: except automatic segmentation regulates, control system is also designed with manual adjustments function, ensure that manual intervention if desired.
5. control method as sectional-regulated in the auxiliary feedwater flow in claim 1-4 as described in any one, it is characterized in that: after auxiliary feedwater flow control valve enters sectional-regulated pattern, when the liquid level of steam generator reaches two position setting value, the regulating stage by stage of control system to auxiliary feedwater flow control valve is as follows:
When the liquid level of steam generator reaches high setting value, the aperture of variable valve is adjusted to 5 ~ 40%;
When the liquid level of steam generator reaches low setting value, the aperture of variable valve is adjusted to 80 ~ 100%;
When steam generator liquid level is between two position setting value, controller keeps previous moment to export, and the aperture of variable valve is constant;
Auxiliary feedwater variable valve will be in sectional-regulated pattern always, until there is reset signal, exit shaping modes, and variable valve returns to standard-sized sheet position.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
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CN201510009327.XA CN104681111A (en) | 2015-01-08 | 2015-01-08 | Auxiliary water supply flow segmented regulation control method |
GB1522104.7A GB2535834B (en) | 2015-01-08 | 2015-12-15 | Method for segmental control of auxillary feedwater flow |
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CN201510009327.XA CN104681111A (en) | 2015-01-08 | 2015-01-08 | Auxiliary water supply flow segmented regulation control method |
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CN104681111A true CN104681111A (en) | 2015-06-03 |
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CN201510009327.XA Pending CN104681111A (en) | 2015-01-08 | 2015-01-08 | Auxiliary water supply flow segmented regulation control method |
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GB (1) | GB2535834B (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN107895599A (en) * | 2017-10-12 | 2018-04-10 | 中广核研究院有限公司 | A kind of voltage-stablizer water level measurement method and voltage-stablizer |
CN109581923A (en) * | 2018-12-05 | 2019-04-05 | 深圳中广核工程设计有限公司 | Nuclear power station feed water control system |
CN111486438A (en) * | 2020-03-18 | 2020-08-04 | 中国核电工程有限公司 | Control method for preventing overflow of steam generator caused by auxiliary water supply system |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6021169A (en) * | 1998-10-22 | 2000-02-01 | Abb Combustion Engineering Nuclear Power, Inc. | Feedwater control over full power range for pressurized water reactor steam generators |
US20050072380A1 (en) * | 2003-07-19 | 2005-04-07 | Korea Power Engineering Company, Inc. | Feedwater control system considering pressure drop of feedwater control valve in nuclear power plant and control method therefor |
CN103050161A (en) * | 2012-12-11 | 2013-04-17 | 中国核电工程有限公司 | Method for automatically isolating auxiliary water supply pipeline |
CN203338776U (en) * | 2013-07-30 | 2013-12-11 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
CN103474108A (en) * | 2013-09-03 | 2013-12-25 | 中国核电工程有限公司 | Safe replenishment method of auxiliary water supply system |
CN203882632U (en) * | 2014-03-26 | 2014-10-15 | 中国核电工程有限公司 | Nuclear power plant main feed-water flow adjustment system |
Family Cites Families (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5780182A (en) * | 1980-11-07 | 1982-05-19 | Hitachi Ltd | Minimum-flow control system for condensate system |
JPH11271491A (en) * | 1998-03-24 | 1999-10-08 | Toshiba Corp | Reactor feed water controller |
US7120218B2 (en) * | 2002-09-25 | 2006-10-10 | Westinghouse Electric Co, Llc | Method for calibrating steam generator water level measurement |
JP5964029B2 (en) * | 2011-10-26 | 2016-08-03 | 三菱重工業株式会社 | Auxiliary feed valve control device for steam generator |
CN104696943A (en) * | 2013-12-09 | 2015-06-10 | 徐州传庆电子科技有限公司 | Safe and automatic heating and water feeding device for boiler |
-
2015
- 2015-01-08 CN CN201510009327.XA patent/CN104681111A/en active Pending
- 2015-12-15 GB GB1522104.7A patent/GB2535834B/en active Active
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6021169A (en) * | 1998-10-22 | 2000-02-01 | Abb Combustion Engineering Nuclear Power, Inc. | Feedwater control over full power range for pressurized water reactor steam generators |
US20050072380A1 (en) * | 2003-07-19 | 2005-04-07 | Korea Power Engineering Company, Inc. | Feedwater control system considering pressure drop of feedwater control valve in nuclear power plant and control method therefor |
CN103050161A (en) * | 2012-12-11 | 2013-04-17 | 中国核电工程有限公司 | Method for automatically isolating auxiliary water supply pipeline |
CN203338776U (en) * | 2013-07-30 | 2013-12-11 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
CN103474108A (en) * | 2013-09-03 | 2013-12-25 | 中国核电工程有限公司 | Safe replenishment method of auxiliary water supply system |
CN203882632U (en) * | 2014-03-26 | 2014-10-15 | 中国核电工程有限公司 | Nuclear power plant main feed-water flow adjustment system |
Non-Patent Citations (1)
Title |
---|
成军 等: "AP1000与M310改进型压水堆二回路给水系统比较分析", 《华电技术》 * |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN107895599A (en) * | 2017-10-12 | 2018-04-10 | 中广核研究院有限公司 | A kind of voltage-stablizer water level measurement method and voltage-stablizer |
CN109581923A (en) * | 2018-12-05 | 2019-04-05 | 深圳中广核工程设计有限公司 | Nuclear power station feed water control system |
CN109581923B (en) * | 2018-12-05 | 2021-10-15 | 深圳中广核工程设计有限公司 | Water supply control system for nuclear power station |
CN111486438A (en) * | 2020-03-18 | 2020-08-04 | 中国核电工程有限公司 | Control method for preventing overflow of steam generator caused by auxiliary water supply system |
Also Published As
Publication number | Publication date |
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GB201522104D0 (en) | 2016-01-27 |
GB2535834A (en) | 2016-08-31 |
GB2535834B (en) | 2019-04-10 |
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Application publication date: 20150603 |