CN107084011A - A kind of nuclear steam turbine method for rapid cooling - Google Patents
A kind of nuclear steam turbine method for rapid cooling Download PDFInfo
- Publication number
- CN107084011A CN107084011A CN201710277713.6A CN201710277713A CN107084011A CN 107084011 A CN107084011 A CN 107084011A CN 201710277713 A CN201710277713 A CN 201710277713A CN 107084011 A CN107084011 A CN 107084011A
- Authority
- CN
- China
- Prior art keywords
- unit
- steam turbine
- pressure cylinder
- rapid cooling
- vapour source
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D25/00—Component parts, details, or accessories, not provided for in, or of interest apart from, other groups
- F01D25/08—Cooling; Heating; Heat-insulation
- F01D25/12—Cooling
Landscapes
- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Control Of Turbines (AREA)
Abstract
The invention discloses a kind of nuclear steam turbine method for rapid cooling, including：Off-the-line unit, makes unit no-load running；Cut off the heating vapour source of one-level reheater or the heating vapour source of two grades of reheaters；When the unit no-load running time is T, lock is made.In the present invention, due to having cut off the heating vapour source of one-level reheater or the heating vapour source of two grades of reheaters, air inlet vapour source temperature into intermediate pressure cylinder is reduced, intermediate pressure cylinder cylinder temperature is quickly reduced, again because intermediate pressure cylinder and high pressure cylinder are arranged for association type, the quick reduction of intermediate pressure cylinder cylinder temperature also results in the quickly reduction of high pressure cylinder cylinder temperature.Compared to the mode of natural cooling, the Cooling Mode in the present invention can make high pressure cylinder and intermediate pressure cylinder be quickly reduced to the temperature value of setting.
Description
Technical field
The present invention relates to nuclear power field, more specifically to a kind of nuclear steam turbine method for rapid cooling.
Background technology
Conventional thermal power plant is shut down typically using sliding parameter operation, and tune is reached by adjusting the method for main steam pressure and temperature
The purpose of whole load.Steam turbine load declines with the reduction of steam parameter, and steam turbine high-pressure cylinder metal temperature also accordingly declines.
But, for nuclear power plant's Steam Turbine, because nuclear island main steam pressure remains stable, it is impossible to performed with reference to aforesaid way and shut down behaviour
Make.When the steam turbine to nuclear power plant is overhauled and is maintained, it is necessary first to steam turbine high-pressure cylinder and intermediate pressure cylinder is cooled down.
In the prior art, the type of cooling of steam turbine high-pressure cylinder and intermediate pressure cylinder is in unit trip and beats natural cooling after lock.It is very bright
Aobvious, the time needed for natural cooling is longer, so as to just extend maintenance duration.
Therefore, how to realize the quick cooling of nuclear steam turbine, so as to shorten maintenance duration, be those skilled in the art urgently
Critical problem to be solved.
The content of the invention
It is an object of the invention to provide a kind of nuclear steam turbine method for rapid cooling, so as to shorten maintenance duration.
To reach above-mentioned purpose, the present invention provides following technical scheme：
A kind of nuclear steam turbine method for rapid cooling, including：
Off-the-line unit, makes unit no-load running；
Cut off the heating vapour source of one-level reheater or the heating vapour source of two grades of reheaters；
When the unit no-load running time is T, lock is made.
Preferably, described " the heating vapour source of cut-out one-level reheater or the heating vapour source of two grades of reheaters " is closing one
The isolating valve or the isolating valve of two grades of reheaters of level reheater.
Preferably, the off-the-line unit when the power of the assembling unit is less than 10%Pn.
Preferably, the off-the-line unit when the power of the assembling unit is 8%Pn.
Preferably, described " the off-the-line unit when the power of the assembling unit is 8%Pn " includes：Into after refrigerating mode, device to be controlled
When detecting the power of the assembling unit for 8%Pn, controller control disconnection device off-the-line unit.
Preferably, described " isolating valve for closing the isolating valve or two grades of reheaters of one-level reheater " includes：It is to be controlled
Device is detected after unit trip signal, controls the isolating valve of one-level reheater or the isolating valve of two grades of reheaters to close.
Preferably, described " when the unit no-load running time is T, making lock " includes：Controller controls disconnection device off-the-line machine
After group, controller starts timing, when timing is to T, and controller control makes brake gear and makes lock.
Preferably, T≤3 hour.
It can be seen from the above technical proposal that in order that the high pressure cylinder and intermediate pressure cylinder of nuclear steam turbine are quickly cooled down, at this
In invention, off-the-line unit first makes unit no-load running, cuts off the heating vapour source or two grades of reheating of one-level reheater again afterwards
The heating vapour source of device.Finally make lock.Due to having cut off the heating vapour source of one-level reheater or the heating vapour source of two grades of reheaters,
Air inlet vapour source temperature into intermediate pressure cylinder is reduced, and intermediate pressure cylinder cylinder temperature is quickly reduced, and because intermediate pressure cylinder and high pressure cylinder are association type
Arrangement, the quick reduction of intermediate pressure cylinder cylinder temperature also results in the quickly reduction of high pressure cylinder cylinder temperature.Compared to the mode of natural cooling, this hair
Cooling Mode in bright can make high pressure cylinder and intermediate pressure cylinder be quickly reduced to the temperature value of setting.
Brief description of the drawings
Scheme in order to illustrate the embodiments of the present invention more clearly, below by using required for described in embodiment
Accompanying drawing is briefly described, it should be apparent that, drawings in the following description are only some embodiments of the present invention, for ability
For field technique personnel, on the premise of not paying creative work, other accompanying drawings can also be obtained according to these accompanying drawings.
The structural representation for the steam turbine that Fig. 1 provides for the specific embodiment of prior art one；
The flow chart for the nuclear steam turbine method for rapid cooling that Fig. 2 provides for a specific embodiment of the invention；
The flow chart for the nuclear steam turbine method for rapid cooling that Fig. 3 provides for another specific embodiment of the present invention.
Wherein, 1 it is reactor steam generator, 2 be high pressure cylinder, 3 be intermediate pressure cylinder, 4 be separator, 5 is two
Level reheater, 6 be one-level reheater, 7 be pipeline, 8 be pipeline, 9 be pipeline, 10 be pipeline, 11 be pipeline.
Embodiment
The invention provides a kind of nuclear steam turbine method for rapid cooling, so as to shorten maintenance duration.
Below in conjunction with the accompanying drawing in the embodiment of the present invention, the technical scheme in the embodiment of the present invention is carried out clear, complete
Site preparation is described, it is clear that described embodiment is only a part of embodiment of the present invention, rather than whole embodiments.Base
In embodiments of the invention, those of ordinary skill in the art obtained on the premise of creative work is not made it is all its
Its embodiment, belongs to the scope of protection of the invention.
Refer to high pressure cylinder 2 and intermediate pressure cylinder 3 in Fig. 1, nuclear steam turbine is combined structure.Nuclear steam turbine has vapour
Water separator/heater 4, separator 4 has one-level reheater 6 and two grades of reheaters 5.Some vapor in high pressure cylinder 2
One-level reheater 6 is entered by pipeline 9 as heating vapour source.Main steam from reactor steam generator 1 is used as heating vapour
Source enters two grades of reheaters 5.Initial steam expansion working in high pressure cylinder 2, is discharged, and enter vapour by pipeline 8 and pipeline 7 afterwards
Water separator/heater 4, separator 4 carries out steam-water separation to steam, steam is changed into superheated steam.Steam-water separation is again
Superheated steam in hot device 4 enters intermediate pressure cylinder 3 by pipeline 10 and pipeline 11.
It refer to accompanying drawing 2.In a specific embodiment of the invention, nuclear steam turbine method for rapid cooling includes following step
Suddenly：Off-the-line unit, makes unit no-load running.Two grades of reheaters 5 of heating vapour source or cut-out of one-level reheater 6 are cut off afterwards
Heat vapour source.The vapor (steam) temperature of the entrance intermediate pressure cylinder 3 thus made is quickly reduced, so that the cylinder temperature of intermediate pressure cylinder 3 is quickly reduced.
When the unit no-load running time is T, lock is made, forces and appraises and decides steam turbine stopping.Why unloaded fortune is limited in the present embodiment
The capable time, is that the humidity of steam is larger because steam cannot get sufficient steam-water separation when unit is unloaded, if empty for a long time
Carrying row, can cause damage to low pressure (LP) cylinder and blade.Therefore, typically by the no-load running time restriction of unit within 6 hours.
In the present embodiment, off-the-line unit first, makes unit no-load running, cuts off the heating of one-level reheater 6 again afterwards
The heating vapour source of vapour source or two grades of reheaters 5.Finally make lock.Due to having cut off the heating vapour source or two of one-level reheater 6
The heating vapour source of level reheater 5, the air inlet vapour source temperature into intermediate pressure cylinder 3 is reduced, and the cylinder temperature of intermediate pressure cylinder 3 is quickly reduced, and due to
Intermediate pressure cylinder 3 and high pressure cylinder 2 arrange that the quick reduction of the cylinder temperature of intermediate pressure cylinder 3 also results in the fast prompt drop of the cylinder temperature of high pressure cylinder 2 for association type
It is low.Compared to the mode of natural cooling, the Cooling Mode in the present embodiment can make high pressure cylinder 2 and the fast prompt drop of intermediate pressure cylinder 3
The low temperature value to setting.
Further, since the temperature of the heating vapour source in two grades of reheaters 5 is higher than the heating vapour source in one-level reheater 6
Temperature, therefore, cut-out two grades of reheaters 5 heating vapour source can make intermediate pressure cylinder 3 cylinder temperature decline faster, using cut off two grades again
The mode of the heating vapour source of hot device 5 can shift to an earlier date 1.4 angel's high pressure cylinders 2 and intermediate pressure cylinder 3 is reduced to setting compared to natural cooling
Temperature value, unit can generate electricity 1400MW in 1.4 days.
Isolating valve is provided with one-level reheater 6 and two grades of reheaters 5, therefore can be by closing one-level reheater 6
Isolating valve reach the purpose of the heating vapour source of cut-out one-level reheater 6；Reached by closing the isolating valve of two grades of reheaters 5
To the purpose of the heating vapour source of two grades of reheaters 5 of cut-out.
When being more than or equal to 10%Pn due to the power of the assembling unit, reactor easily occurs jumping heap phenomenon.Therefore, in order to avoid reaction
Heap jumps the generation of heap phenomenon, provides when the power of the assembling unit is less than 10%Pn to implement in the present invention in a specific embodiment of the invention
Method for rapid cooling, carry out the operation such as unit trip.
Further, off-the-line unit when the prioritizing selection power of the assembling unit is 8%Pn.Because below 10%Pn the first platform
It is exactly 8%Pn, and in 8%Pn power, core physics have corresponding experiment.
In a specific embodiment of the invention, controller is additionally arranged, the controller is electrically connected with disconnection device, disconnection device
For group " specifically include：Into after refrigerating mode, when device to be controlled detects the power of the assembling unit for 8%Pn, controller control off-the-line
Device off-the-line unit.In the present embodiment, controller can automatically control disconnection device and remove off-the-line unit, so as to reduce artificial labor
Momentum.
In a specific embodiment of the invention, controller also with the isolating valve of one-level reheater 6 or with two grades of reheaters 5
Isolating valve electrical connection.After after unit trip, unit trip signal can be fed back to controller." one-level reheating is closed in above-mentioned
The isolating valve of the isolating valve of device 6 or two grades of reheaters 5 " includes：Device to be controlled is detected after unit trip signal, controller control
The isolating valve of the isolating valve of one-level reheater 6 processed or two grades of reheaters 5 is closed.
In a specific embodiment of the invention, controller has clocking capability.In above-mentioned " the unit no-load running time is
During T, lock is made " include：After controller control disconnection device off-the-line unit, controller starts timing, when timing is to T, controller
Control makes brake gear and makes lock.Lock process is beaten by controller is completed automatically in the present embodiment, is further increased automatic
Change degree.
The time general control of steam turbine no-load running is within 6 hours.But, Steam Turhine Adjustment during steam turbine is unloaded
There is obvious pulse in system servomotor power oil pressure, to mitigate damage of the pulse to steam turbine control system servomotor flexible pipe,
In a specific embodiment of the invention, T≤3 hour are provided, i.e. steam turbine no-load running time zero load is within 3 hours.
In summary, into after refrigerating mode, controller detects whether unit operation power is 8%Pn first, if not,
Wait；If it is, controller controls disconnection device off-the-line unit, unit no-load running, while controller starts timing.It is to be controlled
Device is received after the feedback signal of disconnection device, and controller controls the isolating valve of two grades of reheaters 5 to close.Controller is detected afterwards
Whether timing reaches T, if not, waiting；If it is, controller control makes brake gear and makes lock, unit is forced to shut down.
The described above of the disclosed embodiments, enables professional and technical personnel in the field to realize or using the present invention.It is right
A variety of modifications of these embodiments will be apparent for those skilled in the art, and as defined herein one
As principle can realize in other embodiments without departing from the spirit or scope of the present invention.Therefore, the present invention will
It will not be intended to be limited to the embodiments shown herein, and be to fit to consistent with principles disclosed herein and features of novelty
Most wide scope.
Claims (8)
1. a kind of nuclear steam turbine method for rapid cooling, it is characterised in that including：
Off-the-line unit, makes unit no-load running；
Cut off the heating vapour source of one-level reheater or the heating vapour source of two grades of reheaters；
When the unit no-load running time is T, lock is made.
2. nuclear steam turbine method for rapid cooling according to claim 1, it is characterised in that " the cut-out one-level reheating
The heating vapour source of the heating vapour source of device or two grades of reheaters " is the isolating valve or two grades of reheaters for closing one-level reheater
Isolating valve.
3. nuclear steam turbine method for rapid cooling according to claim 2, it is characterised in that be less than 10% in the power of the assembling unit
Off-the-line unit during Pn.
4. nuclear steam turbine method for rapid cooling according to claim 3, it is characterised in that in the power of the assembling unit be 8%Pn
Shi Xielie units.
5. nuclear steam turbine method for rapid cooling according to claim 4, it is characterised in that described " to be in the power of the assembling unit
Off-the-line unit during 8%Pn " includes：Into after refrigerating mode, when device to be controlled detects the power of the assembling unit for 8%Pn, controller control
Disconnection device off-the-line unit processed.
6. nuclear steam turbine method for rapid cooling according to claim 5, it is characterised in that described " to close one-level reheating
The isolating valve of the isolating valve of device or two grades of reheaters " includes：Device to be controlled is detected after unit trip signal, and control one-level is again
The isolating valve of the isolating valve of hot device or two grades of reheaters is closed.
7. nuclear steam turbine method for rapid cooling according to claim 5, it is characterised in that " the unit no-load running
When time is T, lock is made " include：After controller control disconnection device off-the-line unit, controller starts timing, when timing is to T,
Controller control makes brake gear and makes lock.
8. nuclear steam turbine method for rapid cooling according to claim 1, it is characterised in that T≤3 hour.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710277713.6A CN107084011B (en) | 2017-04-25 | 2017-04-25 | A kind of nuclear steam turbine method for rapid cooling |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710277713.6A CN107084011B (en) | 2017-04-25 | 2017-04-25 | A kind of nuclear steam turbine method for rapid cooling |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN107084011A true CN107084011A (en) | 2017-08-22 |
| CN107084011B CN107084011B (en) | 2019-05-31 |
Family
ID=59613125
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201710277713.6A Active CN107084011B (en) | 2017-04-25 | 2017-04-25 | A kind of nuclear steam turbine method for rapid cooling |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN107084011B (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109869199A (en) * | 2019-01-31 | 2019-06-11 | 山西河坡发电有限责任公司 | A kind of steam turbine structure and low pressure (LP) cylinder cut cylinder control method |
| CN113464215A (en) * | 2021-07-27 | 2021-10-01 | 辽宁红沿河核电有限公司 | Low-power cooling method and system for high and medium pressure cylinder of steam turbine |
| CN113707349A (en) * | 2021-09-18 | 2021-11-26 | 福建宁德核电有限公司 | Method and device for measuring leakage of main steam pipe of CPR1000 unit |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104989467A (en) * | 2015-08-06 | 2015-10-21 | 阳江核电有限公司 | Steam turbine shutdown cooling control method |
| CN106523044A (en) * | 2016-12-22 | 2017-03-22 | 广东核电合营有限公司 | Cylinder temperature acceleration cooling method of nuclear power station steam turbine high/medium-pressure cylinder |
-
2017
- 2017-04-25 CN CN201710277713.6A patent/CN107084011B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104989467A (en) * | 2015-08-06 | 2015-10-21 | 阳江核电有限公司 | Steam turbine shutdown cooling control method |
| CN106523044A (en) * | 2016-12-22 | 2017-03-22 | 广东核电合营有限公司 | Cylinder temperature acceleration cooling method of nuclear power station steam turbine high/medium-pressure cylinder |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109869199A (en) * | 2019-01-31 | 2019-06-11 | 山西河坡发电有限责任公司 | A kind of steam turbine structure and low pressure (LP) cylinder cut cylinder control method |
| CN109869199B (en) * | 2019-01-31 | 2021-03-02 | 山西河坡发电有限责任公司 | Steam turbine structure and low-pressure cylinder cutting control method |
| CN113464215A (en) * | 2021-07-27 | 2021-10-01 | 辽宁红沿河核电有限公司 | Low-power cooling method and system for high and medium pressure cylinder of steam turbine |
| CN113707349A (en) * | 2021-09-18 | 2021-11-26 | 福建宁德核电有限公司 | Method and device for measuring leakage of main steam pipe of CPR1000 unit |
| CN113707349B (en) * | 2021-09-18 | 2023-06-02 | 福建宁德核电有限公司 | CPR1000 unit main steam pipeline leakage measurement method and device |
Also Published As
| Publication number | Publication date |
|---|---|
| CN107084011B (en) | 2019-05-31 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN107120149B (en) | The method and system of newly-built supercritical unit is debugged using external activated vapor | |
| CN107165686B (en) | Secondary reheating thermal power generating unit bypass control method and system | |
| CN101846311A (en) | The system and method for preheating heat recovery steam generator and the jet chimney that is associated | |
| CN107084011B (en) | A kind of nuclear steam turbine method for rapid cooling | |
| CN108757068B (en) | Combined cycle steam turbine set total cut heat supply control method and device | |
| JP2000161014A (en) | Combined power generator facility | |
| EP3450705A1 (en) | Gas turbine combined cycle system equipped with control device and its control method | |
| CN101825005A (en) | Method for controlling the operation of high-voltage bypass in thermal generator set | |
| KR101710636B1 (en) | Controlling apparatus and starting method | |
| CN106958465B (en) | A method of for fast and stable rotating speed after Turbo-generator Set removal of load | |
| CN103595041A (en) | Monitoring device for rapid load reduction of power plant set and method thereof | |
| CN108104888A (en) | A kind of power grid frequency modulation system and method based on frequency modulation bypass | |
| CN110131004A (en) | The control method and device of Combined cycle gas-steam turbine Unit Commitment peak regulation | |
| CN206711612U (en) | A kind of system for verifying HTGR start and stop heaping equipment function | |
| JP2009293871A (en) | Start bypass system in steam power generation facility and its operating method | |
| CN106322346B (en) | A kind of method of direct current cooker sliding parameter blowing out | |
| JPH0241715B2 (en) | ||
| JPS5823208A (en) | Operation controller for thermal power plant equipped with stored steam power generation system | |
| JPS5918211A (en) | Starting control method of steam turbine | |
| CN107889514B (en) | Method for cooling a steam turbine | |
| CN105431909B (en) | Method during extension for controlling pressurized-water reactor | |
| KR20210081847A (en) | Combined heat and power system operable in case of load loss of turbine generator | |
| CN111255531B (en) | Method for testing load switch of steam inlet valve of steam turbine of nuclear power station and determining parameters of steam inlet valve | |
| CN113266817B (en) | Method for preventing and controlling overtemperature of superheater tube wall | |
| JP2008304264A (en) | Nuclear power plant and its operation method |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |