CN104616709B - Safety and stability control method based on asynchronous oscillation of nuclear power units - Google Patents
Safety and stability control method based on asynchronous oscillation of nuclear power units Download PDFInfo
- Publication number
- CN104616709B CN104616709B CN201510035159.1A CN201510035159A CN104616709B CN 104616709 B CN104616709 B CN 104616709B CN 201510035159 A CN201510035159 A CN 201510035159A CN 104616709 B CN104616709 B CN 104616709B
- Authority
- CN
- China
- Prior art keywords
- power
- nuclear power
- power units
- safety
- unit
- 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
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/12—Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
-
- 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
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)
- Control Of Eletrric Generators (AREA)
Abstract
The invention relates to control methods of nuclear power units, particularly to a safety and stability control method based on asynchronous oscillation of nuclear power units. The method is characterized by comprising computing the asynchronous oscillation control strategy of the nuclear power units in advance, and setting the set value of the control strategy into a safety automatic device; performing generator tripping through combined control of a stream turbine side and a nuclear island side in a manner of tripping the corresponding boosting variable high-voltage side breakers of the nuclear power unit. The safety and stability control method based on asynchronous oscillation of the nuclear power units is achieved through mutual cooperation of precise starting of the safety automatic device, effective control of a steam turbine regulating system to a steam turbine and a stream turbine bypass exhaust system, and precise execution provided by a reactor control system. Compared with the prior art, the safety and stability control method based on asynchronous oscillation of nuclear power units has the advantage that, when asynchronous oscillation of the nuclear power units occur, by effectively, precisely, timely and reasonably controlling the steam turbine side and the nuclear island side, the technical problem that the nuclear power units participate safety and stability control during asynchronous oscillation can be solved, so that the nuclear power units can participate in transient-state safety and stability control and meanwhile safe and stable operation of the nuclear power units can be ensured.
Description
Technical field
The present invention relates to a kind of control method of nuclear power generating sets, particularly a kind of safety based on nuclear power generating sets asynchronous oscillation
Stable control method, the security and stability control being primarily adapted for use in during the outlet circuit generation asynchronous oscillation of pressurized-water reactor nuclear power plant.
Background technology
In power system, it is ensured that the safe and stable operation of power system is a matter of the last importance.Modern electric
System is improved constantly due to unit capacity, and electrical network scale constantly expands, and electric pressure is improved constantly, supertension long distance power transmission with
And interconnected network is formed, make electric network composition more complicated, cause the security and stability control of modern power systems more and more difficult.
If the generated output of Large Copacity power plant can not send into load center nearby, conveyed by long distance powedr transmission passage, electricity
Caused by gas distance increase, electromotor synchronizing torque or damping torque are reduced, and are broken down in circuit or other electric network elements
When may result in the problem that generating set is vibrated relative to Out of step.According to《Guiding rules of power system safety and stability》DL755
Regulation, when power system occur second level safety and stability standard major break down disturb when, when generating set relative to electrical network lose
Step oscillation problem occurs, if asynchronous oscillation is still suffered from after protection, switch and reclosing correct operation, the machine of cutting must be taken to arrange
Apply.
As requirement of the nuclear power generating sets to safety is high, control system is complicated, generally there is safety and stability in electrical network and ask
All try one's best during topic and avoid cutting off nuclear power generating sets, nuclear power generating sets all do not participate in the security and stability control of electrical network for a long time.
The part nuclear power generating sets for accessing electrical network at present also occur in that asking for asynchronous oscillation when nuclear power plant sends line fault
Topic, and the pattern of asynchronous oscillation be nuclear power generating sets relative to other unit asynchronous oscillations in electrical network, must now take excision
The measure of nuclear power generating sets, exerting oneself for the nuclear power generating sets of step-out is reduced to into zero safe and stable operation that just can guarantee that electrical network rapidly,
And the unit for cutting off other power plant cannot also make power system restoration stable.
The security and stability control function of above-mentioned nuclear power generating sets is by automatic safety device, steam turbine control system and reaction
Heap controls bar system to realize, however, when nuclear power generating sets occur asynchronous oscillation, how to adjust to automatic safety device, steam turbine
Section system and reactor control rod system be controlled become with the safe and stable operation for ensureing electrical network and nuclear power generating sets it is new
Technical barrier, does not propose corresponding solution in prior art.
The content of the invention
It is an object of the invention to can effectively, in time, reliably according to one kind is provided in place of the deficiencies in the prior art
Security and stability control method based on nuclear power generating sets asynchronous oscillation.
The purpose of the present invention is realized by following approach：
The security and stability control method of nuclear power generating sets asynchronous oscillation, which is characterized by, and comprises the steps：
1）According to the method for operation of electrical network, including normal operating mode and various maintenance runs, by simulation calculation
Obtain the security and stability control strategy definite value during forecast failure collection of its correspondence generation nuclear power generating sets asynchronous oscillation；
2）By the security and stability control strategy fixed value adjusting for being obtained in automatic safety device；
3）Automatic safety device is being judged by the electric current of monitoring nuclear power plant outlet, voltage and circuit breaker position information
After line failure and meet sending out to cut machine order and jump when cutting machine condition and losing for set security and stability control strategy definite value
Step unit boosts accordingly and becomes high-pressure side chopper；
4）Machine is cut by the execution that jointly controls of steamer pusher side and nuclear island side, method is as follows：
When automatic safety device by tripping step-out unit boost accordingly change high-pressure side chopper cut machine when, whole nuclear power
Unit completely disengages from electrical network, Turbo-generator Set band station-service load operation；Generator outlet chopper GCB is closed, turbine generator
Unit continues to generate electricity, by house transformer conveying supply station-service load；Reactor control system is automatic by reactor nucleus power
Adjust in 30%Pn, control rod is inserted to reduce core power；According to the situation of islet operation, follow-up control strategy is divided into two
Kind：
（1）If islet operation success --- steam turbine band station-service load operation success, core power are reduced to 30% from 100%Pn
Pn low power runs, turbine by-pass exhaust system are in temp-controled mode, and the time restriction of control rod insertion is 12 hours,
If unit band station-service load operation more than 12 hours, needs control rod to be carried entirely to heap top, and carries out boronation maintenance low-power
Level, takes long-term low power operational mode；During low power run, unit band station-service load waits electrical network to process event
Barrier, after power system restoration is normal, reactor just can power per liter, grid-connected again.
（2）Islet operation is unsuccessful --- as tripping boosting becomes on high-tension side chopper, lose main factory
External power, if steam turbine band station-service load operation is unsuccessful, Main Condensate Pump will be stopped transport, and the main feedwater of steam generator will be lost；
As in nuclear power plant, two machines constitute one group of operation, when steam turbine band station-service load operation it is unsuccessful, if adjacent
The main transformer of unit normally runs, and unit public load is switched to adjacent unit and is powered to reduce the load that auxiliary becomes, and passed through
Auxiliary becomes a main coolant pump of the startup separator of falling power transmission unit to recover coolant forced circulation, steam generator feed water by
Auxiliary feedwater system is supplied, in the case where no other accidents occur, by set steady in hot shutdown 24 hours to wait
Power system restoration；
If adjacent unit main transformer is stopped transport, two unit public loads can not switch to adjacent unit and power, can only switch
Power to emergency power supply；If auxiliary becomes not surpass held, two unit public loads are switched to into auxiliary and becomes power supply, and by auxiliary
Wherein one main coolant pump for becoming the startup separator of falling power transmission unit is helped to recover coolant forced circulation, steam generator feedwater
Supplied by auxiliary feedwater system；In the case where no other accidents occur, by set steady hot shutdown 24 hours so as to etc.
Treat power system restoration；
If adjacent unit main transformer is stopped transport, and auxiliary transformer also surpasses appearance, and the main coolant pump of failure unit can not start,
Primary Ioops keep Natural Circulation, steam generator feedwater to be supplied by auxiliary feedwater system；As primary Ioops lose forced circulation, this
When set steady hot shutdown condition time be 2 hours；In 2 hours, electrical network does not recover, and carries out Core cooling, and continue etc.
Treat power system restoration；
Electrical network is waited to process failure, the normal reactor afterwards of power system restoration just can power per liter, grid-connected again.
Asynchronous oscillation control strategy of the present invention by calculated in advance nuclear power generating sets, and control strategy setting valve is arranged on
In automatic safety device, when there is asynchronous oscillation in nuclear power generating sets by steamer pusher side and nuclear island side it is effective, accurate, and
When, rationally control, taken into full account the control condition of automatic safety device, steam turbine control system and reactor control rod system
And control program, the technical barrier of security and stability control is participated in when solving nuclear power generating sets asynchronous oscillation, is participated in nuclear power generating sets
Electrical network transient safe and stable ensure that the safe and stable operation of nuclear power generating sets while control.
Description of the drawings
Fig. 1 show the schematic flow sheet of the security and stability control method of nuclear power generating sets asynchronous oscillation of the present invention；
Fig. 2 show described in the embodiment of the present invention jump step-out unit boost accordingly change high-pressure side chopper cut nuclear power generating sets
（Islet operation success）Control flow chart；
Fig. 3 show described in the embodiment of the present invention by jump step-out unit boost accordingly change high-pressure side chopper cut nuclear power
Unit（Islet operation is unsuccessful）Control flow.
The present invention is described further with reference to embodiment.
Specific embodiment
Most preferred embodiment：
The present invention provides a kind of security and stability control method of nuclear power generating sets asynchronous oscillation, the peace of nuclear power generating sets asynchronous oscillation
Full stable control process schematic diagram is as shown in figure 1, comprise the following steps：
Step one：Calculate asynchronous oscillation security and stability control strategy definite value：Based on the various possible methods of operation of electrical network, wrap
Normal operating mode and various maintenance runs are included, the forecast failure collection for nuclear power generating sets asynchronous oscillation may occur is calculated
Corresponding security and stability control strategy definite value；
Step 2：By security and stability control strategy fixed value adjusting in automatic safety device；
Step 3：Automatic safety device passes through to monitor the information such as electric current, voltage and the circuit breaker position of nuclear power plant's outlet,
After judging line failure and meet Policy Table when cutting machine condition send out cut machine order jump step-out unit boost accordingly
Become high-pressure side chopper；
Step 4：Machine is cut by the execution that jointly controls of steamer pusher side and nuclear island side, its mode is by tripping step-out
Unit boost accordingly become high-pressure side chopper mode carry out cutting machine.
Wherein it is by way of tripping unit boosts change high-pressure side chopper accordingly to carry out the control flow for cutting machine such as
Fig. 2, shown in 3, its main control process is as follows：
When automatic safety device becomes high-pressure side chopper by tripping boosting cuts machine, whole nuclear power generating sets completely disengage from electricity
Net, Turbo-generator Set band station-service load operation.GCB is closed, and Turbo-generator Set can continue to generate electricity, by house transformer
Conveying supply station-service load.As steam turbine load declines to a great extent, unnecessary steam is arranged by turbine by-pass exhaust system action
Toward condenser.Control rod is inserted to reduce core power by reactor nucleus power automatic adjusting in 30%Pn.According to islet operation
Situation, follow-up control strategy are divided into two kinds：
(1) if islet operation success --- steam turbine band station-service load operation success, core power are reduced to 30% from 100%Pn
Pn low power runs, turbine by-pass exhaust system are in temp-controled mode, and its control flow chart is as shown in Figure 2.Control rod
The time restriction of insertion is 12 hours, if unit band station-service load operation more than 12 hours, needs control rod to be carried entirely to heap
Top, and boronation maintenance lower power levels are carried out, take long-term low power operational mode.Either control rod insertion still adopts boron
Change and maintain low power run, during low power run, unit band station-service load waits electrical network to process failure, and power system restoration is just
After often, reactor just can power per liter, grid-connected again.If there is other accidents during low power run, into NS/
RRA patterns (NS is cooling normal shutdown pattern, and RRA is reactor RHR system), carry out Core cooling.
(2) islet operation is unsuccessful --- as tripping boosting becomes on high-tension side chopper, lose main factory
External power, if steam turbine band station-service load operation is unsuccessful, Main Condensate Pump will be stopped transport, and the main feedwater of steam generator will be lost, its
Control flow chart is as shown in Figure 3.
In nuclear power plant, two machines constitute one group of operation, and part station-service load is that two units are public.If steam turbine band factory
It is unsuccessful with load operation, if the main transformer of adjacent unit normally runs, two unit public loads can be switched to adjacent machine
Group power supply is to reduce the load that auxiliary becomes, and becomes a main coolant pump of the startup separator of falling power transmission unit to recover by auxiliary
Coolant forced circulation, steam generator feedwater are supplied by auxiliary feedwater system.In the case where no other accidents occur, will
Set steady is in hot shutdown 24 hours to wait power system restoration.If electrical network in 24 hours does not recover, unit will be into NS/
RRA patterns, carry out Core cooling, and continue waiting for power system restoration.
If adjacent unit main transformer is stopped transport, two unit public loads can not switch to adjacent unit and power, can only switch
Power to emergency power supply.If auxiliary becomes not surpass held, two unit public loads are switched to into auxiliary and becomes power supply, and by auxiliary
Wherein one main coolant pump for becoming the startup separator of falling power transmission unit is helped to recover coolant forced circulation, steam generator feedwater
Supplied by auxiliary feedwater system.In the case where no other accidents occur, by set steady hot shutdown 24 hours so as to etc.
Treat power system restoration.If electrical network in 24 hours does not recover, unit will carry out Core cooling into NS/RRA patterns, and continue etc.
Treat power system restoration.
If adjacent unit main transformer is stopped transport, and auxiliary transformer also surpasses appearance, and the main coolant pump of failure unit can not start,
Primary Ioops keep Natural Circulation, steam generator feedwater to be supplied by auxiliary feedwater system；As primary Ioops lose forced circulation, this
When set steady hot shutdown condition time be 2 hours, in 2 hours electrical network do not recover then enter NS/RRA patterns, carry out heap
Core is cooled down, and continues waiting for power system restoration.
Electrical network is waited to process failure, the normal reactor afterwards of power system restoration just can power per liter, grid-connected again.
The not described part of the present invention is same as the prior art.
Claims (1)
1. the security and stability control method based on nuclear power generating sets asynchronous oscillation, it is characterised in that comprise the steps：
1）According to the method for operation of electrical network, including normal operating mode and various maintenance runs, obtain its correspondence and core occurs
Security and stability control strategy definite value during the forecast failure collection of group of motors asynchronous oscillation；
2）By the security and stability control strategy fixed value adjusting for being obtained in automatic safety device；
3）Automatic safety device is judging circuit by the electric current of monitoring nuclear power plant outlet, voltage and circuit breaker position information
After breaking down and meet sending out when cutting machine condition for set security and stability control strategy definite value and cut machine order, jump step-out machine
The corresponding boosting of group becomes high-pressure side chopper；
4）Machine is cut by the execution that jointly controls of steamer pusher side and nuclear island side, method is as follows：
When automatic safety device becomes high-pressure side chopper by tripping boosting cuts machine, whole nuclear power generating sets completely disengage from electrical network,
Turbo-generator Set band station-service load operation；Generator outlet chopper GCB is closed, and Turbo-generator Set continues to generate electricity, and passes through
House transformer conveying supply station-service load；Reactor nucleus power automatic adjusting in 30%Pn, will be controlled by reactor control system
Rod inserts to reduce core power；According to the situation of islet operation, follow-up control strategy is divided into two kinds：
(1) if islet operation success --- steam turbine band station-service load operation success, it is low that core power is reduced to 30%Pn from 100%Pn
Power operation, turbine by-pass exhaust system are in temp-controled mode, and the time restriction of control rod insertion is 12 hours, if
Unit band station-service load operation more than 12 hours, then need control rod to be carried entirely to heap top, and carries out boronation maintenance lower power levels,
Take long-term low power operational mode；During low power run, unit band station-service load waits electrical network to process failure, electrical network
Recover it is normal after reactor just can power per liter, grid-connected again；
(2) islet operation is unsuccessful --- as tripping boosting becomes on high-tension side chopper, lose main factory's dispatch from foreign news agency
Source, if steam turbine band station-service load operation is unsuccessful, Main Condensate Pump will be stopped transport, and the main feedwater of steam generator will be lost；
As in nuclear power plant, two machines constitute one group of operation, when steam turbine band station-service load operation it is unsuccessful, if adjacent unit
Main transformer normally run, unit public load is switched to into adjacent unit and is powered to reduce the load of auxiliary transformer, and
By a main coolant pump of the auxiliary transformer startup separator of falling power transmission unit recovering coolant forced circulation, steam generation
Device feedwater is supplied by auxiliary feedwater system, in the case where no other accidents occur, by set steady in hot shutdown 24 hours
To wait power system restoration；
If adjacent unit main transformer is stopped transport, two unit public loads can not switch to adjacent unit and power, can only switch
Power to emergency power supply；If auxiliary transformer does not surpass and holds, two unit public loads are switched to into auxiliary transformer and are powered,
And steamed with recovering coolant forced circulation by wherein one main coolant pump of the auxiliary transformer startup separator of falling power transmission unit
Vapour generator feedwater is supplied by auxiliary feedwater system；In the case where no other accidents occur, by set steady in hot shutdown
24 hours to wait power system restoration；
If adjacent unit main transformer is stopped transport, and auxiliary transformer also surpasses appearance, and the main coolant pump of failure unit can not start,
Primary Ioops keep Natural Circulation, steam generator feedwater to be supplied by auxiliary feedwater system；As primary Ioops lose forced circulation, this
When set steady hot shutdown condition time be 2 hours；In 2 hours, electrical network does not recover, and carries out Core cooling, and continue etc.
Treat power system restoration；
Electrical network is waited to process failure, the normal reactor afterwards of power system restoration just can power per liter, grid-connected again.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510035159.1A CN104616709B (en) | 2015-01-23 | 2015-01-23 | Safety and stability control method based on asynchronous oscillation of nuclear power units |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510035159.1A CN104616709B (en) | 2015-01-23 | 2015-01-23 | Safety and stability control method based on asynchronous oscillation of nuclear power units |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104616709A CN104616709A (en) | 2015-05-13 |
| CN104616709B true CN104616709B (en) | 2017-04-26 |
Family
ID=53151126
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201510035159.1A Active CN104616709B (en) | 2015-01-23 | 2015-01-23 | Safety and stability control method based on asynchronous oscillation of nuclear power units |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104616709B (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108155653A (en) * | 2016-12-06 | 2018-06-12 | 苏州热工研究院有限公司 | A kind of stability control equipment auxiliary control method and system for nuclear power plant |
| CN109147976A (en) * | 2017-06-16 | 2019-01-04 | 苏州热工研究院有限公司 | A kind of stability control equipment applied to nuclear power station cuts machine method |
| CN107845436B (en) * | 2017-09-27 | 2023-11-14 | 中国核电工程有限公司 | Remote shutdown station control method for main control room of pressurized water reactor nuclear power plant when not being resident |
| CN113936830A (en) * | 2021-09-22 | 2022-01-14 | 广东核电合营有限公司 | Nuclear power plant generator set state control method and electronic equipment |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2001147294A (en) * | 1999-11-24 | 2001-05-29 | Hitachi Ltd | Power generator facility |
| EP1438724A1 (en) * | 2001-10-11 | 2004-07-21 | Pebble Bed Modular Reactor (Proprietary) Limited | A method of operating a nuclear power plant |
| US7961835B2 (en) * | 2005-08-26 | 2011-06-14 | Keller Michael F | Hybrid integrated energy production process |
| CN103166249B (en) * | 2011-12-14 | 2016-03-16 | 深圳市康必达中创科技有限公司 | A kind of rapid combination system safety stable control method |
| CN203118515U (en) * | 2012-09-25 | 2013-08-07 | 上海发电设备成套设计研究院 | Pressurized water reactor nuclear power plant conventional island adapted for peak load regulation of power grid |
| CN103595127B (en) * | 2013-09-18 | 2015-05-06 | 中国海洋石油总公司 | Intelligent control method for offshore petroleum platform power grid |
-
2015
- 2015-01-23 CN CN201510035159.1A patent/CN104616709B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN104616709A (en) | 2015-05-13 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104633638B (en) | The integrated control method of the shutdown not blowing out function of power plant FCB | |
| CN104616709B (en) | Safety and stability control method based on asynchronous oscillation of nuclear power units | |
| CN103730906B (en) | A kind of control method for coordinating suppressing Hybrid HVDC commutation failure | |
| CN107465255B (en) | A kind of Turbo-generator Set accident starting auxiliary Power switching method and system | |
| CN102035217B (en) | Control method for actively preventing simultaneous low-voltage tripping of sets in wind power field | |
| CN105703401A (en) | Emergency control method suitable for wind/photovoltaic power station | |
| CN104795113B (en) | A kind of chaser to nuclear power station unit station jumps the method and system that heap carries out risk assessment | |
| CN112628711A (en) | Auxiliary engine fault stable combustion control method based on 600MW supercritical unit low load | |
| CN104637558B (en) | Safe and stable control method for asynchronous oscillation of nuclear power unit | |
| CN108134404B (en) | Wind power generating set high voltage crossing control method and device | |
| CN206195453U (en) | Million units do not have high -pressure stand -by power supply's quick recovering start -up system | |
| CN105863745B (en) | The control method of shunt tripping steam turbine during a kind of grid-connected transformer unit gate out switch tripping operation | |
| CN107171288A (en) | A kind of fired power generating unit zero energy protects system and method | |
| Venmathi et al. | Impact of grid connected distributed generation on voltage sag | |
| CN107492913A (en) | Isolated network power station PMS power management systems | |
| CN111934326A (en) | Method and system for coordinately controlling high voltage ride through of wind generating set | |
| CN114019372A (en) | First loading capacity check test method for emergency security diesel generator of thermal power plant | |
| CN113658733A (en) | Control system device of nuclear turbine and control method thereof | |
| Shi et al. | Study on the faults of nuclear power plant and effects on transient stability of power system | |
| JP2005201834A (en) | Nuclear power plant and method for operating it | |
| JP2016059168A (en) | Bus voltage stabilizer | |
| CN206922422U (en) | A kind of single line of power plant sends out line fault protection system | |
| CN111384707A (en) | Supplementary trip device and method for ultrahigh-voltage combined switching station of nuclear power plant | |
| CN109193806A (en) | A method of for assessing generator loss-of-excitation protection and electric network coordination relationship | |
| CN112350333B (en) | Control method and device suitable for FCB triggering under isolated network operation |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C41 | Transfer of patent application or patent right or utility model | ||
| CB03 | Change of inventor or designer information |
Inventor after: Cai Xiaoling Inventor after: Jia Wenge Inventor after: Tan Shengsheng Inventor after: Cui Gang Inventor after: Zhang Xingzhen Inventor after: Liu Renhe Inventor after: Huang Xufeng Inventor after: Zhuang Xiong Inventor after: Lin Hong Inventor after: Huang Wei Inventor after: Sun Hui Inventor after: Di Changchun Inventor after: Xiong Jingchuan Inventor before: Cai Xiaoling Inventor before: Liu Renhe Inventor before: Huang Xufeng Inventor before: Zhuang Xiong Inventor before: Lin Hong |
|
| COR | Change of bibliographic data | ||
| TA01 | Transfer of patent application right |
Effective date of registration: 20170126 Address after: 350003 Gulou District, Fujian, Fuzhou No. 54 Road, No. 268 Applicant after: Fujian Electric Power Survey and Design Institute Applicant after: China General Nuclear Power Corporation Applicant after: China Nuclear Power Engineering Co., Ltd. Address before: 350003 Gulou District, Fujian, Fuzhou No. 54 Road, No. 268 Applicant before: Fujian Electric Power Survey and Design Institute |
|
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder |
Address after: 350003 Gulou District, Fujian, Fuzhou No. 54 Road, No. 268 Co-patentee after: China General Nuclear Power Corporation Patentee after: China Electric Power Construction Group Fujian electric survey and Design Institute Co., Ltd. Co-patentee after: China Nuclear Power Engineering Co., Ltd. Address before: 350003 Gulou District, Fujian, Fuzhou No. 54 Road, No. 268 Co-patentee before: China General Nuclear Power Corporation Patentee before: Fujian Electric Power Survey and Design Institute Co-patentee before: China Nuclear Power Engineering Co., Ltd. |
|
| CP01 | Change in the name or title of a patent holder |