CN117542554A - Method for maintaining reactor after turbine shutdown - Google Patents
Method for maintaining reactor after turbine shutdown Download PDFInfo
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- CN117542554A CN117542554A CN202311559321.0A CN202311559321A CN117542554A CN 117542554 A CN117542554 A CN 117542554A CN 202311559321 A CN202311559321 A CN 202311559321A CN 117542554 A CN117542554 A CN 117542554A
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- deaerator
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- 238000000034 method Methods 0.000 title claims abstract description 30
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 65
- 238000010438 heat treatment Methods 0.000 claims abstract description 34
- 230000001105 regulatory effect Effects 0.000 claims abstract description 27
- 230000001052 transient effect Effects 0.000 claims abstract description 7
- 239000007788 liquid Substances 0.000 claims abstract description 4
- 230000003111 delayed effect Effects 0.000 claims abstract 2
- 238000012423 maintenance Methods 0.000 claims description 12
- 238000007599 discharging Methods 0.000 claims description 4
- 238000013461 design Methods 0.000 abstract description 2
- 230000000694 effects Effects 0.000 abstract description 2
- 230000035939 shock Effects 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 230000001276 controlling effect Effects 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
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- 238000010586 diagram Methods 0.000 description 1
- 238000005485 electric heating Methods 0.000 description 1
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- 230000014509 gene expression Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
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- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Control Of Turbines (AREA)
Abstract
The invention provides a method for maintaining a reactor after a steam turbine is shut down, which comprises the following steps: after the steam turbine is stopped, the power of the reactor is reduced from the first power to the second power; a main steam pipeline provides a heating steam source for the deaerator; rapidly closing a condensate regulating valve to reduce the amount of cold water entering the deaerator through a condensate pipe; the condensed water regulating valve is opened in a delayed mode, and cold water is provided for the deaerator through a condensed water pipe so as to maintain the liquid level of the deaerator; the steam generated by the steam generator is discharged to the condenser through the main steam pipeline and the bypass pipeline in sequence so as to adjust the outlet pressure of the steam generator; after transient state, the deaerator is supplied with condensed water with the first temperature through the condensed water pipe, and is supplied with main steam through the heating pipeline, so as to maintain that the deaerator conveys the water with the second temperature to the steam generator. The invention has the technical effects of reasonable design, and can maintain the stable operation of the reactor and avoid reactor shutdown.
Description
Technical Field
The invention belongs to the technical field of high-temperature stacks, and particularly relates to a method for maintaining a reactor after a steam turbine is shut down.
Background
Along with the production of a high-temperature reactor, the direct-current steam generator is firstly applied in the nuclear power field, and the direct-current steam generator is applied to a high-steam parameter nuclear power plant in the later period, but has some problems to be overcome:
at present, a spiral coil pipe type design is adopted for the high-temperature reactor. As a key device of a nuclear power plant, the spiral coil belongs to a loop pressure boundary and plays a role in containing the radioactivity of a loop. The weld is relatively sensitive to feedwater temperature, and excessive temperature changes can cause rapid changes in the stress of the steam generator coil weld, which can present a challenge to the integrity of the primary circuit boundary.
Under the accident conditions such as the shutdown of the steam turbine, the low-pressure heater, the deaerator and the high-pressure heater lose the heating steam source, and the high-temperature pile is taken as an example, the water supply temperature is rapidly reduced from 190 ℃ to below 30 ℃, so that huge cold impact can be caused on the direct-current steam, and the pressure boundary of a loop is likely to fail. In order to protect key equipment, only water supply can be isolated, the reactor is stopped, the expansion of accidents and the extension of recovery time are objectively caused, and great hidden trouble is caused for the stable operation of the nuclear power plant.
Disclosure of Invention
The invention aims at solving at least one of the technical problems in the prior art and provides a novel technical scheme of a reactor maintenance method after a steam turbine is stopped.
According to one aspect of the present invention, there is provided a method of maintaining a reactor after a turbine shutdown, comprising the steps of:
step S100, after the steam turbine is stopped, the power of the reactor is reduced from the first power to the second power;
step S200, a main steam pipeline provides a heating steam source for the deaerator; the main steam pipeline is communicated with the deaerator through a heating pipeline;
step S300, a condensate water regulating valve is quickly closed, so that the amount of cold water entering the deaerator through a condensate water pipe is reduced; after a preset time delay, starting the condensed water regulating valve, and providing cold water for the deaerator through a condensed water pipe so as to maintain the liquid level of the deaerator; wherein, the condensed water regulating valve is arranged on the condensed water pipe;
step S400, discharging steam generated by the steam generator to the condenser through the main steam pipeline and the bypass pipeline in sequence so as to adjust the outlet pressure of the steam generator;
step S500, after transient state, supplying condensate water with a first temperature to the deaerator through a condensate pipe, and supplying main steam to the deaerator through a heating pipeline so as to maintain the deaerator to convey water with a second temperature to a steam generator; wherein the first temperature is less than the second temperature.
Optionally, a heating electric regulating valve is arranged on the heating pipeline;
when a main steam pipeline provides a heating steam source for the deaerator, firstly, rapidly opening the heating electric regulating valve, and improving the operating pressure of the deaerator to a first preset pressure; then, the operating pressure of the deaerator is adjusted to be slowly reduced from the first preset pressure to the second preset pressure.
Optionally, after delaying for a preset time, slowly opening the condensate water regulating valve after the heating electric regulating valve reaches a stable opening degree.
Optionally, a bypass valve is arranged on the bypass pipeline;
and opening the side discharge valve, and discharging the main steam in the main steam pipeline to the condenser through the bypass pipeline.
Optionally, the flow ratio of the main steam to the condensate entering the deaerator is 4.9:1.
optionally, the temperature difference between the first temperature and the second temperature is not less than 130 ℃.
Alternatively, the first temperature is 30 ℃; the second temperature was 170 ℃.
Optionally, before the turbine is shut down, the deaerator delivers feedwater to the steam generator at a third temperature; wherein the third temperature is 190 ℃.
Optionally, the first power is 250MW; the second power was 70MW.
Optionally, the first preset pressure is 0.7MPa; the second preset pressure is 0.5MPa.
The invention has the technical effects that:
according to the method for maintaining the reactor after the shutdown of the steam turbine, the accident transient can be relieved under the condition that the steam turbine of the nuclear power plant adopts the direct-current steam generator to shutdown, and the reactor shutdown is avoided.
Meanwhile, the reactor maintaining method heats the water supply in the deaerator through main steam after the steam turbine is shut down, thereby replacing the steam extraction and interruption of the deaerator, well reducing the water supply temperature impact, avoiding the stress on the welding seam of the steam generator and protecting important equipment.
Furthermore, the method for maintaining the reactor after the steam turbine is shut down maintains low-power operation of the reactor through a long-term operation mode, so that the unit can be flushed and turned to grid at any time, the expansion of accidents is avoided, the operation event times are reduced, and the availability of the unit is improved.
In addition, the method for maintaining the reactor after the steam turbine is shut down ensures that the original system has few newly-added equipment and has lower equipment operation and maintenance cost, thereby better protecting important equipment of the system,
the number of times of shutdown is reduced, and the availability of the nuclear power plant unit is improved.
Drawings
FIG. 1 is a schematic flow chart of a method for maintaining a reactor after a steam turbine shutdown according to an embodiment of the present invention;
FIG. 2 is a schematic diagram illustrating the connection of deaerators in a method for maintaining a reactor after a shutdown of a steam turbine according to an embodiment of the present invention.
In the figure: 1. a steam generator; 2. a steam turbine; 3. a condenser; 4. a condensate pump; 5. a low pressure heater; 6. a deaerator; 7. a water feed pump; 8. a high pressure heater; 9. a condensed water regulating valve; 10. heating the electric regulating valve; 11. a side discharge valve; 12. a condensate pipe; 13. a main water supply pipe; 14. a main steam pipe; 15. a heating pipe; 16. and a bypass conduit.
Detailed Description
Various exemplary embodiments of the present application will now be described in detail with reference to the accompanying drawings. It should be noted that: the relative arrangement of the components and steps, numerical expressions and numerical values set forth in these embodiments do not limit the scope of the present application unless it is specifically stated otherwise.
Reference will now be made in detail to embodiments of the present application, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to like or similar elements or elements having like or similar functionality throughout. The embodiments described below by referring to the drawings are exemplary only for the purpose of explaining the present application and are not to be construed as limiting the present application. All other embodiments, which can be made by one of ordinary skill in the art based on the embodiments herein without making any inventive effort, are intended to be within the scope of the present application.
The features of the terms "first", "second", and the like in the description and in the claims of this application may be used for descriptive or implicit inclusion of one or more such features. In the description of the present application, unless otherwise indicated, the meaning of "a plurality" is two or more. Furthermore, in the description and claims, "and/or" means at least one of the connected objects, and the character "/", generally means that the associated object is an "or" relationship.
In the description of the present application, it should be noted that, unless explicitly specified and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be either fixedly connected, detachably connected, or integrally connected, for example; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the terms in this application will be understood by those of ordinary skill in the art in a specific context.
According to one aspect of the present invention, referring to fig. 1 and 2, a method for maintaining a reactor after a turbine is shut down is provided, which is mainly used for maintaining a once-through steam generator and a reactor after a turbine of a nuclear power plant is shut down, so as to avoid unnecessary shutdown. On one hand, the method for maintaining the reactor after the steam turbine is stopped can avoid the great change of the temperature of the feed water after the steam turbine is stopped, and on the other hand, the method provides a loop for taking out the heat of the reactor for a long time, thereby finally realizing the stable operation of the reactor after the steam turbine is stopped.
Specifically, the method for maintaining the reactor after the shutdown of the steam turbine comprises the following steps:
in step S100, after the steam turbine 2 is stopped, the power of the reactor is reduced from the first power to the second power. Wherein the power of the reactor is automatically reduced after the turbine 2 is shut down.
In other embodiments, the power of the reactor may be reduced below the second power as desired.
Step S200, a main steam pipeline 14 provides a heating steam source for the deaerator 6; wherein the main steam line 14 communicates with said deaerator 6 via a heating line 15.
Step S300, the condensed water regulating valve 9 is quickly closed to reduce the amount of cold water entering the deaerator 6 through the condensed water pipe 12; opening the condensate regulating valve 9 after delaying for a preset time, and providing cold water to the deaerator 6 through a condensate pipe 12 to maintain the liquid level of the deaerator 6; wherein the condensate regulating valve 9 is arranged on the condensate pipe 12.
In step S400, the steam generated by the steam generator 1 is sequentially discharged to the condenser 3 through the main steam pipe 14 and the bypass pipe 16 to adjust the outlet pressure of the steam generator 1.
Step S500, after transient state, the condensed water with the first temperature is supplied to the deaerator 6 through the condensed water pipe 12, and main steam is supplied to the deaerator 6 through the heating pipeline 15, so that the deaerator 6 can maintain to convey the water with the second temperature to the steam generator 1; wherein the first temperature is less than the second temperature.
In the embodiment of the application, the method for maintaining the reactor after the shutdown of the steam turbine can relieve accident transient under the condition that the nuclear power plant steam turbine 2 adopting the direct current steam generator 1 is shutdown, and avoid reactor shutdown.
Meanwhile, the reactor maintaining method heats the water supply in the deaerator 6 through the main steam after the steam turbine is shut down, thereby replacing the short-time intermittent supply of the condensed water, well reducing the water supply temperature impact, avoiding the stress on the welding seam of the steam generator 1 and protecting important equipment.
Furthermore, the method for maintaining the reactor after the steam turbine is shut down maintains low-power operation of the reactor through a long-term operation mode, so that the unit can be flushed and turned to grid at any time, the expansion of accidents is avoided, the operation event times are reduced, and the availability of the unit is improved.
In addition, the method for maintaining the reactor after the steam turbine is shut down ensures that the original system has less newly-added equipment and lower equipment operation and maintenance cost, thereby better protecting important equipment of the system, reducing the shutdown times and improving the availability of the nuclear power plant unit.
Optionally, the heating pipeline 15 is provided with a heating electric regulating valve 10;
when the main steam pipeline 14 provides a heating steam source for the deaerator 6, firstly, the heating electric regulating valve 10 is quickly opened, and the operating pressure of the deaerator 6 is increased to a first preset pressure; then, the operating pressure of the deaerator 6 is adjusted to be slowly reduced from the first preset pressure to the second preset pressure. The deaerator 6 is operated stably for a long period of time at a second preset pressure. Of course, the operating pressure of the deaerator 6 may be further reduced below the second preset pressure according to actual needs. For example, the operating pressure of deaerator 6 may be controlled by PID regulation.
Illustratively, the opening of the heating motor-operated regulator valve 10 is given a feed-forward according to a preset nuclear power-valve position characteristic table, and is opened promptly.
In the above embodiment, the heating pipe 15 is connected between the main steam pipe 14 and the deaerator 6, and the steam in the main steam pipe 14 can be introduced into the deaerator 6 to heat the condensed water by controlling the heating electric control valve 10, so that the preheating of the relevant pipes of the deaerator 6 is normally maintained, the cold impact to the steam generator 1 is reduced, and the safety is high.
In addition, the condensate regulating valve 9 is quickly closed to reduce the amount of cold water entering the deaerator 6 through the condensate pipe 12, so that the temperature of the deaerator 6 in a transient state is not greatly reduced, and the difficulty in controlling the operating pressure of the deaerator 6 by heating the electric regulating valve 10 is reduced.
Optionally, after a preset time delay, after the heating electric regulating valve 10 reaches a stable opening degree, the condensate water regulating valve 9 is slowly opened. This helps to maintain the pre-heating of the deaerator 6 normally, ensures the outlet temperature of the deaerator 6, and thus reduces the cold shock to the steam generator 1.
Moreover, by slowly opening the condensate regulating valve 9, it helps to maintain the level of the deaerator 6.
Optionally, a bypass valve 11 is arranged on the bypass pipe 16;
the bypass valve 11 is opened, and the main steam in the main steam pipe 14 is discharged to the condenser 3 through the bypass pipe 16.
Optionally, the flow ratio of main steam to condensate entering the deaerator 6 is 4.9:1.
in the above embodiment, it is effectively ensured that the outlet temperature of the deaerator 6 is maintained at a preset temperature, for example, 160 ℃ for the main feed water temperature, thereby reducing the cold shock to the steam generator 1.
Specifically, the electric heating regulating valve 10 and the condensed water regulating valve 9 are matched to effectively control the flow of steam and condensed water, so that the main water supply temperature can be stably maintained, and the unit is ensured to maintain stable operation.
Optionally, the temperature difference between the first temperature and the second temperature is not less than 130 ℃. The impact of the water supply temperature on the steam generator 1 is effectively reduced, the stress on the welding seam of the steam generator 1 is avoided, and the stable operation of the unit is ensured.
Alternatively, the first temperature is 30 ℃; the second temperature was 170 ℃.
In the above embodiment, the outlet temperature of the deaerator 6 is 170 ℃, so that the feed water temperature impact of the steam generator 1 is reduced from 160 ℃ to 20 ℃, and the steam generator 1 is well protected.
Optionally, the deaerator 6 delivers feedwater at a third temperature to the steam generator 1 before the turbine 2 is shut down; wherein the third temperature is 190 ℃. After the steam turbine is stopped, the temperature of the water supply is reduced from 190 ℃ to 170 ℃ and the temperature difference is 20 ℃, so that the impact on the steam generator 1 caused by the reduction of the temperature of the water supply can be effectively reduced, and the safe and stable operation of the steam generator 1 is ensured.
Optionally, the first power is 250MW; the second power was 70MW. This helps guaranteeing unit safety and stability operation after the steam turbine is shut down, avoids the reactor shutdown.
Optionally, the first preset pressure is 0.7MPa; the second preset pressure is 0.5MPa. This helps to ensure safe and stable operation of the deaerator 6 while providing a suitable temperature of the feed water to the steam generator 1, reducing cold shock to the steam generator 1.
In a specific embodiment, one end of the condensate pipe 12 is connected with the deaerator 6, the other end is connected with the condensate pump 4, and the condensate pipe 12 is provided with the low-pressure heater 5. The condensate pump 4 drives condensate into the condensate pipe 12 and through the several stages of low pressure heaters 5 into the deaerator 6.
Further, one end of the main water supply pipe 13 is connected with the deaerator 6, the other end is connected with the steam generator 1, and the main water supply pipe 13 is provided with the water supply pump 7 and the high-pressure heater 8. The feed water in the deaerator 6 enters the main feed water pipe 13 under the action of the feed water pump 7 and will pass through the several high-pressure heaters 8 into the steam generator 1.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.
Claims (10)
1. A method for maintaining a reactor after a turbine shutdown, comprising the steps of:
step S100, after the steam turbine is stopped, the power of the reactor is reduced from the first power to the second power;
step S200, a main steam pipeline provides a heating steam source for the deaerator; the main steam pipeline is communicated with the deaerator through a heating pipeline;
step S300, a condensate water regulating valve is quickly closed, so that the amount of cold water entering the deaerator through a condensate water pipe is reduced; after a preset time delay, starting the condensed water regulating valve, and providing cold water for the deaerator through a condensed water pipe so as to maintain the liquid level of the deaerator; wherein, the condensed water regulating valve is arranged on the condensed water pipe;
step S400, discharging steam generated by the steam generator to the condenser through the main steam pipeline and the bypass pipeline in sequence so as to adjust the outlet pressure of the steam generator;
step S500, after transient state, supplying condensate water with a first temperature to the deaerator through a condensate pipe, and supplying main steam to the deaerator through a heating pipeline so as to maintain the deaerator to convey water with a second temperature to a steam generator; wherein the first temperature is less than the second temperature.
2. The post-shutdown reactor maintenance method of a steam turbine according to claim 1, wherein a heating electric control valve is provided on the heating pipe;
when a main steam pipeline provides a heating steam source for the deaerator, firstly, rapidly opening the heating electric regulating valve, and improving the operating pressure of the deaerator to a first preset pressure; then, the operating pressure of the deaerator is adjusted to be slowly reduced from the first preset pressure to the second preset pressure.
3. The post-shutdown reactor maintenance method of claim 2, wherein after a predetermined time is delayed, the condensate water control valve is slowly opened after the heating electric control valve reaches a stable opening.
4. The post-shutdown reactor maintenance method of a steam turbine according to claim 1, wherein a bypass valve is provided on the bypass pipe;
and opening the side discharge valve, and discharging the main steam in the main steam pipeline to the condenser through the bypass pipeline.
5. The post turbine shutdown reactor maintenance method of claim 1, wherein a flow ratio of main steam to condensate entering the deaerator is 4.9:1.
6. the post-shutdown reactor maintenance method of claim 1, wherein a temperature difference between the first temperature and the second temperature is not less than 130 ℃.
7. The post-shutdown reactor maintenance method of claim 6, wherein the first temperature is 30 ℃; the second temperature was 170 ℃.
8. The post-shutdown reactor maintenance method of claim 7, wherein the deaerator delivers feedwater to the steam generator at a third temperature prior to shutdown of the steam turbine; wherein the third temperature is 190 ℃.
9. The post-shutdown reactor maintenance method of a steam turbine of claim 1, wherein the first power is 250MW; the second power was 70MW.
10. The post-shutdown reactor maintenance method of a steam turbine of claim 2, wherein the first preset pressure is 0.7MPa; the second preset pressure is 0.5MPa.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311559321.0A CN117542554A (en) | 2023-11-21 | 2023-11-21 | Method for maintaining reactor after turbine shutdown |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311559321.0A CN117542554A (en) | 2023-11-21 | 2023-11-21 | Method for maintaining reactor after turbine shutdown |
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| Publication Number | Publication Date |
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| CN117542554A true CN117542554A (en) | 2024-02-09 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN202311559321.0A Pending CN117542554A (en) | 2023-11-21 | 2023-11-21 | Method for maintaining reactor after turbine shutdown |
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| CN (1) | CN117542554A (en) |
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2023
- 2023-11-21 CN CN202311559321.0A patent/CN117542554A/en active Pending
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