CN107084011B - A kind of nuclear steam turbine method for rapid cooling - Google Patents
A kind of nuclear steam turbine method for rapid cooling Download PDFInfo
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- CN107084011B CN107084011B CN201710277713.6A CN201710277713A CN107084011B CN 107084011 B CN107084011 B CN 107084011B CN 201710277713 A CN201710277713 A CN 201710277713A CN 107084011 B CN107084011 B CN 107084011B
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- steam turbine
- level
- reheater
- pressure cylinder
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- 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
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- 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, comprising: off-the-line unit makes unit idle running；Cut off the heating vapour source of level-one reheater or the heating vapour source of second level reheater；When the unit idle running time is T, lock is made.In the present invention, due to having cut off the heating vapour source of level-one reheater or the heating vapour source of second level reheater, air inlet vapour source temperature into intermediate pressure cylinder reduces, intermediate pressure cylinder cylinder temperature quickly reduces, again since intermediate pressure cylinder and high pressure cylinder are association type arrangement, the quick reduction of intermediate pressure cylinder cylinder temperature, which also results in high pressure cylinder cylinder temperature, quickly to be reduced.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 fields, more specifically to a kind of nuclear steam turbine method for rapid cooling.
Background technique
Conventional thermal power plant, which is shut down, generally to be run using sliding parameter, reaches tune 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 nuclear power plant's Steam Turbine can not be executed referring to aforesaid way because nuclear island main steam pressure maintains to stablize 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 be made to cool down.
In the prior art, the type of cooling of steam turbine high-pressure cylinder and intermediate pressure cylinder is in unit trip and to beat natural cooling after lock.It is very bright
Aobvious, the time needed for natural cooling is longer, to just extend maintenance duration.
Therefore, how to realize the rapid cooling of nuclear steam turbine, so as to shorten maintenance duration, be those skilled in the art urgently
Critical problem to be solved.
Summary of the invention
The object of the present invention is to provide a kind of nuclear steam turbine method for rapid cooling, so as to shorten maintenance duration.
In order to achieve the above objectives, the present invention the following technical schemes are provided:
A kind of nuclear steam turbine method for rapid cooling, comprising:
Off-the-line unit makes unit idle running；
Cut off the heating vapour source of level-one reheater or the heating vapour source of second level reheater；
When the unit idle running time is T, lock is made.
Preferably, described " the heating vapour source of cutting level-one reheater or the heating vapour source of second level reheater " is to close one
The grade isolating valve of reheater or the isolating valve of second 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: the device to be controlled into after refrigerating mode
When detecting that the power of the assembling unit is 8%Pn, controller controls disconnection device off-the-line unit.
Preferably, described " isolating valve for closing the isolating valve or second level reheater of level-one reheater " includes: to be controlled
After device detects unit trip signal, the isolating valve of the isolating valve or second level reheater that control level-one reheater is closed.
Preferably, described " when the unit idle running time is T, making lock " includes: controller control disconnection device off-the-line machine
After group, controller starts timing, and when timing is to T, controller control makes brake gear and makes lock.
Preferably, T≤3 hour.
It can be seen from the above technical proposal that the high pressure cylinder and intermediate pressure cylinder in order to make nuclear steam turbine are quickly cooled down, at this
In invention, off-the-line unit first makes unit idle running, cuts off the heating vapour source or second level reheating of level-one reheater again later
The heating vapour source of device.Finally make lock.Due to having cut off the heating vapour source of level-one reheater or the heating vapour source of second level reheater,
Air inlet vapour source temperature into intermediate pressure cylinder reduces, and intermediate pressure cylinder cylinder temperature quickly reduces, and since intermediate pressure cylinder and high pressure cylinder are association type
Arrangement, the quick reduction of intermediate pressure cylinder cylinder temperature, which also results in high pressure cylinder cylinder temperature, quickly to be reduced.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.
Detailed description of the invention
Scheme in order to illustrate the embodiments of the present invention more clearly, below will be required to describing in embodiment
Attached drawing is briefly described, it should be apparent that, drawings in the following description are only some embodiments of the invention, for ability
For field technique personnel, without creative efforts, it is also possible to obtain other drawings based on these drawings.
Fig. 1 is the structural schematic diagram for the steam turbine that one specific embodiment of the prior art provides；
Fig. 2 is the flow chart for the nuclear steam turbine method for rapid cooling that a specific embodiment of the invention provides；
Fig. 3 is the flow chart for the nuclear steam turbine method for rapid cooling that another specific embodiment of the present invention provides.
Wherein, 1 it is reactor steam generator, 2 be high pressure cylinder, 3 be intermediate pressure cylinder, 4 be separator, 5 is two
Grade reheater, 6 be level-one reheater, 7 be pipeline, 8 be pipeline, 9 be pipeline, 10 be pipeline, 11 be pipeline.
Specific embodiment
The present invention provides a kind of nuclear steam turbine method for rapid cooling, so as to shorten maintenance duration.
Following will be combined with the drawings in the embodiments of the present invention, and technical solution in the embodiment of the present invention carries out clear, complete
Site preparation description, it is clear that described embodiment is only a part of the embodiments of the present invention, instead of all the embodiments.Base
In the embodiment of the present invention, those of ordinary skill in the art without making creative work it is obtained it is all its
Its embodiment, shall fall within the protection scope of the present invention.
Referring to FIG. 1, the high pressure cylinder 2 and intermediate pressure cylinder 3 in nuclear steam turbine are combined structure.Nuclear steam turbine has vapour
Water separator/heater 4, separator 4 have level-one reheater 6 and second level reheater 5.Some vapor in high pressure cylinder 2
Level-one reheater 6 is entered by pipeline 9 as heating vapour source.Main steam from reactor steam generator 1 is as heating vapour
Source enters second level reheater 5.Initial steam expansion working in high pressure cylinder 2 is discharged by pipeline 8 and pipeline 7 later, and enters vapour
Water separator/heater 4, separator 4 carry out steam-water separation to steam, steam are made to become superheated steam.Steam-water separation is again
Superheated steam in hot device 4 enters intermediate pressure cylinder 3 by pipeline 10 and pipeline 11.
Please refer to attached drawing 2.In a specific embodiment of the invention, nuclear steam turbine method for rapid cooling includes following step
Rapid: off-the-line unit makes unit idle running.The heating vapour source of level-one reheater 6 is cut off later or cuts off second level reheater 5
Heat vapour source.The vapor (steam) temperature into intermediate pressure cylinder 3 thus made quickly reduces, so that making the cylinder temperature of intermediate pressure cylinder 3 quickly reduces.
When the unit idle 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, steam cannot get sufficient steam-water separation when being because of unit zero load, and the humidity of steam is larger, if empty for a long time
Carrying row can cause to damage to low pressure (LP) cylinder and blade.Therefore, generally by the idle running time restriction of unit within 6 hours.
In the present embodiment, off-the-line unit first, makes unit idle running, cuts off the heating of level-one reheater 6 again later
The heating vapour source of vapour source or second level reheater 5.Finally make lock.Due to having cut off the heating vapour source or two of level-one reheater 6
The heating vapour source of grade reheater 5, the air inlet vapour source temperature into intermediate pressure cylinder 3 reduce, and 3 cylinder temperature of intermediate pressure cylinder quickly reduces, and due to
Intermediate pressure cylinder 3 and high pressure cylinder 2 are association type arrangement, and the quick reduction of 3 cylinder temperature of intermediate pressure cylinder also results in the 2 fast prompt drop of cylinder temperature of high pressure cylinder
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
As low as the temperature value of setting.
In addition, the heating vapour source being higher than in level-one reheater 6 due to the temperature of the heating vapour source in second level reheater 5
Temperature, therefore, the heating vapour source of cutting second level reheater 5 can be such that the cylinder temperature of intermediate pressure cylinder 3 declines faster, again using cutting second level
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 in level-one reheater 6 and second level reheater 5, therefore can be by closing level-one reheater 6
Isolating valve come achieve the purpose that cut off level-one reheater 6 heating vapour source；It is reached by closing the isolating valve of second level reheater 5
To the purpose of the heating vapour source of cutting second level reheater 5.
When being more than or equal to 10%Pn due to the power of the assembling unit, reactor, which is easy to appear, jumps heap phenomenon.Therefore, in order to avoid reaction
Heap jumps the generation of heap phenomenon, and regulation is implemented in the present invention when the power of the assembling unit is less than 10%Pn 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 selecting the power of the assembling unit preferentially as 8%Pn.Because of 10%Pn the first platform below
It is exactly 8%Pn, and core physics have corresponding test in 8%Pn power.
In a specific embodiment of the invention, it is additionally arranged controller, which is electrically connected with disconnection device, disconnection device
For group " it specifically includes: after entering refrigerating mode, when device to be controlled detects that the power of the assembling unit is 8%Pn, controller controls off-the-line
Device off-the-line unit.In the present embodiment, controller can automatically control disconnection device and remove off-the-line unit, to reduce artificial labor
Momentum.
In an of the invention specific embodiment, controller also with the isolating valve of level-one reheater 6 or with second level reheater 5
Isolating valve electrical connection.After unit trip, unit trip signal can be fed back to controller." closing level-one reheating among the above
The isolating valve of device 6 or the isolating valve of second level reheater 5 " includes: controller control after device to be controlled detects unit trip signal
The isolating valve of level-one reheater 6 processed or the isolating valve of second level reheater 5 are closed.
In a specific embodiment of the invention, controller has clocking capability.Among the above " the unit idle running time is
When T, make lock " include: controller control disconnection device off-the-line unit after, controller starts timing, when timing is to T, controller
Control makes brake gear and makes lock.The lock process of beating in the present embodiment is completed automatically by controller, is further improved automatic
Change degree.
The time general control of steam turbine idle running is within 6 hours.But Steam Turhine Adjustment during steam turbine zero load
System oil motor power oil pressure is there are apparent pulse, for the damage for mitigating pulse pair steam turbine control system oil motor hose,
, it is specified that T≤3 hour, i.e., the zero load of steam turbine idle running time is within 3 hours in a specific embodiment of the invention.
In conclusion controller detects whether unit operation power is 8%Pn first into after refrigerating mode, if not,
It waits；If so, controller controls disconnection device off-the-line unit, unit idle running, while controller starts timing.It is to be controlled
After device receives the feedback signal of disconnection device, the isolating valve that controller controls second level reheater 5 is closed.Controller is detected later
Whether timing reaches T, if not, waiting；If so, controller control makes brake gear and makes lock, unit is forced to shut down.
The above description of the disclosed embodiments, enables those skilled in the art to implement or use the present invention.It is right
A variety of modifications of these embodiments will be readily apparent to 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 the principles and novel features disclosed herein
Widest scope.
Claims (8)
1. a kind of nuclear steam turbine method for rapid cooling characterized by comprising
Off-the-line unit makes unit idle running；
The heating vapour source of second level reheater is cut off, the second level reheater is connected to steam generator；
When the unit idle running time is T, lock is made.
2. nuclear steam turbine method for rapid cooling according to claim 1, which is characterized in that " the cutting second level reheating
The heating vapour source of device " is the isolating valve for closing second level reheater.
3. nuclear steam turbine method for rapid cooling according to claim 2, which is characterized in that in the power of the assembling unit less than 10%
Off-the-line unit when Pn.
4. nuclear steam turbine method for rapid cooling according to claim 3, which is characterized in that the power of the assembling unit be 8%Pn
Shi Xielie unit.
5. nuclear steam turbine method for rapid cooling according to claim 4, which is characterized in that described " to be in the power of the assembling unit
Off-the-line unit when 8%Pn " include: into after refrigerating mode, device to be controlled detect the power of the assembling unit be 8%Pn when, controller control
Disconnection device off-the-line unit processed.
6. nuclear steam turbine method for rapid cooling according to claim 5, which is characterized in that described " to close second level reheating
The isolating valve of device " includes: after device to be controlled detects unit trip signal, and the isolating valve of control second level reheater is closed.
7. nuclear steam turbine method for rapid cooling according to claim 5, which is characterized in that " the unit idle running
When time is T, make lock " it include: after controller controls 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, which is characterized in that T≤3 hour.
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| CN201710277713.6A CN107084011B (en) | 2017-04-25 | 2017-04-25 | A kind of nuclear steam turbine method for rapid cooling |
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| CN201710277713.6A CN107084011B (en) | 2017-04-25 | 2017-04-25 | A kind of nuclear steam turbine method for rapid cooling |
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| CN107084011B true CN107084011B (en) | 2019-05-31 |
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| 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 |
| 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 |
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 |
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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 |
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