CN116734317A - Method for exiting working condition of tripping heating system of main water supply pump under nuclear energy large-scale heating working condition - Google Patents
Method for exiting working condition of tripping heating system of main water supply pump under nuclear energy large-scale heating working condition Download PDFInfo
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- CN116734317A CN116734317A CN202310599334.4A CN202310599334A CN116734317A CN 116734317 A CN116734317 A CN 116734317A CN 202310599334 A CN202310599334 A CN 202310599334A CN 116734317 A CN116734317 A CN 116734317A
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- Prior art keywords
- heating
- heat supply
- turbine
- working condition
- heating system
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 24
- 238000010438 heat treatment Methods 0.000 title claims description 48
- 238000000034 method Methods 0.000 title claims description 17
- 230000001960 triggered effect Effects 0.000 claims abstract description 10
- 230000000694 effects Effects 0.000 abstract description 2
- 238000000605 extraction Methods 0.000 description 2
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 1
- 229910002090 carbon oxide Inorganic materials 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F24—HEATING; RANGES; VENTILATING
- F24D—DOMESTIC- OR SPACE-HEATING SYSTEMS, e.g. CENTRAL HEATING SYSTEMS; DOMESTIC HOT-WATER SUPPLY SYSTEMS; ELEMENTS OR COMPONENTS THEREFOR
- F24D19/00—Details
- F24D19/10—Arrangement or mounting of control or safety devices
- F24D19/1006—Arrangement or mounting of control or safety devices for water heating systems
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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
- F01D17/00—Regulating or controlling by varying flow
- F01D17/10—Final actuators
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K11/00—Plants characterised by the engines being structurally combined with boilers or condensers
- F01K11/02—Plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K13/00—General layout or general methods of operation of complete plants
- F01K13/02—Controlling, e.g. stopping or starting
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Thermal Sciences (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Control Of Steam Boilers And Waste-Gas Boilers (AREA)
Abstract
The heat supply system heats the heat supply network circulating water from the steam exhaust pipe of the high-pressure cylinder of the steam turbine in a pressurized mode, then the heat supply system is supplied to the secondary heat exchange station, when the power of the generator is more than 80.7%, the unit is in a reactor-following control mode, the steam turbine is in an LL control mode, the ICV is in a high-exhaust pressure control mode, the reactor thermal power is 100%, when the power of the generator is less than or equal to 80.7%, one main water supply pump trips, at the moment, an RB signal of the steam turbine is triggered, the heat supply system is triggered to exit from a heat supply working condition after time delay is 5 seconds, and the heat supply system is triggered to slowly exit after time delay is 5 seconds, so that the technical effect of preventing fluctuation of the load of the unit can be achieved.
Description
Technical Field
The invention relates to the field of nuclear energy heat supply, in particular to a method for exiting a main water supply pump tripping heat supply system under a nuclear energy large-scale heat supply working condition.
Background
At present, a central heating system is commonly adopted in cities, but heating energy sources are mainly fossil energy sources, and the influence of carbon oxide emission on the environment is difficult to avoid. The nuclear energy is used as clean, efficient and stable energy, continuous heat can be provided for users, and nuclear energy heat supply is becoming another energy supply type of nuclear energy gradually. The existing nuclear power unit externally supplies heat, after a main water supply pump trips under a heat supply working condition, the steam turbine exits the heat supply system in the process of rapidly reducing the power, the influence of the exiting heat supply system on the unit needs to be considered, if the steam which originally flows to a heat supply network heater is inappropriately selected, the steam can rapidly enter a low-pressure cylinder of the steam turbine, and the safety operation of the steam turbine can be influenced. Therefore, the method has important significance for researching the heat supply exit scheme after the pump of the water supply pump jumps.
Disclosure of Invention
The invention provides a method for exiting a main water supply pump tripping heating system under a nuclear energy large-scale heating working condition, which is used for solving the technical problems that the heat supply steam quantity of large-scale heating is larger and accounts for more than 1/3 of the steam inlet quantity of a low-pressure cylinder, the strength of the low-pressure cylinder is influenced, and a turbine is possibly caused to vibrate, so that the machine unit is stopped and the reactor is stopped under a transient working condition of one water supply pump tripping during external heating of a nuclear power heating machine set.
The technical scheme for solving the technical problems is as follows: the heat supply system heats the heat supply network circulating water from the steam turbine high-pressure cylinder steam exhaust pipe in a pressurized mode, then the heat supply system is supplied to the secondary heat exchange station, and when a main water supply pump trips, the heat supply system exits the heat supply working condition, and the heat supply system specifically comprises the following steps: (1) tripping a main feed pump to trigger a turbine RB signal; and (2) triggering the heating system to exit the heating working condition after the delay time is 5 s.
After triggering the turbine RB signal, the turbine load drops at a rate of 100% rated load/min.
When the turbine RB signal is triggered for 18 seconds, the turbine load drops to the target value.
And the GV opening degree is reduced to the target opening degree when the turbine RB signal is triggered for 18 seconds.
And when the load of the steam turbine is 70%, the heat supply system completely exits the heat supply working condition.
During the load drop of the turbine in 0-18 seconds, 4 ECVs are slowly closed.
When the power of the generator is less than or equal to 80.7%, one main water feeding pump trips.
When the power of the generator is more than 80.7%, the unit is in a reactor-to-turbine control mode, and the steam turbine is in a LL control mode.
The heating system includes a steam side system that releases heat and a circulating water side system that absorbs heat.
Detailed Description
The invention provides a method for a main water supply pump tripping heating system to exit the working condition under the nuclear energy large-scale heating working condition, wherein the heating system heats the heat supply network circulating water from a steam exhaust pipe of a high-pressure cylinder of a steam turbine in a pressurizing way, then the heat supply system is supplied to a secondary heat exchange station, when the power of a generator is more than 80.7%, a unit is in a reactor-following control mode, the steam turbine is in a LL control mode, an ICV is in a high-discharge pressure control mode, the reactor thermal power is 100%, when the power of the generator is less than or equal to 80.7%, a main water supply pump trips, at the moment, a turbine RB signal is triggered, the heating system is triggered to exit the heating working condition after time delay is 5 seconds, the heating system is triggered to slowly exit after time delay is 5 seconds, and the technical effect of preventing fluctuation of the load of the unit can be prevented; after triggering the turbine RB signal, the turbine load is reduced at the rate of 100% of rated load per minute, the turbine load is reduced to 70% in 18 seconds, the GV opening is reduced to the target opening, and the heating system completely exits the heating working condition. During the load drop of the turbine in 0-18 seconds, 4 ECVs are slowly closed.
The heat supply system comprises an exothermic steam side system and an endothermic circulating water side system, and specifically comprises a heat supply network heating steam system, a heat supply network circulating water system and a heat supply network heater drainage system.
The English abbreviation RB=run Back used in the invention, and the Chinese term is auxiliary fault load reduction; gv=tuning Valve, chinese term is high pressure cylinder admission regulator Valve; ecv= Extraction steamcontrol valve, chinese term steam extraction regulating valve; icv=inter Valve, chinese term low pressure cylinder admission regulator.
While embodiments of the present invention have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the present disclosure, and that variations, modifications, alternatives to the above embodiments may be made by one of ordinary skill in the art within the scope of the present disclosure.
Claims (10)
1. A method for exiting a main water supply pump tripping heating system under a nuclear energy large-scale heating condition is characterized by comprising the following steps: the heat supply system heats the heat supply network circulating water from the steam turbine high-pressure cylinder steam exhaust pipe in a pressurized mode, then the heat supply system is supplied to the secondary heat exchange station, and when a main water supply pump trips, the heat supply system exits the heat supply working condition, and the heat supply system specifically comprises the following steps:
(1) Tripping a main feed pump to trigger a turbine RB signal;
(2) And triggering the heating system to exit the heating working condition after the delay time is 5 s.
2. The method for exiting a main feedwater pump trip heating system during nuclear power mass heating conditions of claim 1, wherein: after triggering the turbine RB signal in step (1), the turbine load drops at a rate of 100% rated load/min.
3. The method for exiting a main feedwater pump trip heating system during nuclear energy mass heating conditions of claim 2, wherein: when the turbine RB signal is triggered for 18 seconds, the turbine load drops to the target value.
4. The method for exiting a main feedwater pump trip heating system during nuclear energy mass heating conditions of claim 2, wherein: and the GV opening degree is reduced to the target opening degree when the turbine RB signal is triggered for 18 seconds.
5. A method of operating a main feedwater pump trip heating system exit for nuclear energy mass heating as claimed in any of claims 2-3, wherein: and when the load of the steam turbine is 70%, the heat supply system completely exits the heat supply working condition.
6. A method of operating a main feedwater pump trip heating system exit for nuclear energy mass heating as defined in any one of claims 3-4, wherein: during the load drop of the turbine in 0-18 seconds, 4 ECVs are slowly closed.
7. The method for exiting a main feedwater pump trip heating system during nuclear power mass heating conditions of claim 1, wherein: when the power of the generator is less than or equal to 80.7%, one main water feeding pump trips.
8. The method for exiting a main feedwater pump trip heating system during nuclear power mass heating conditions of claim 7, wherein: when the power of the generator is more than 80.7%, the unit is in a reactor-to-turbine control mode, and the steam turbine is in a LL control mode.
9. A method of operating a primary feedwater pump trip heating system exit for nuclear energy mass heating as defined in any one of claims 1-4, wherein: the heating system includes an exothermic vapor side system and an endothermic circulating water side system.
10. The method for exiting a main feedwater pump trip heating system during nuclear power mass heating conditions of claim 9, wherein: the heating system comprises a heat supply network heating steam system, a heat supply network circulating water system and a heat supply network heater drainage system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310599334.4A CN116734317A (en) | 2023-05-25 | 2023-05-25 | Method for exiting working condition of tripping heating system of main water supply pump under nuclear energy large-scale heating working condition |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310599334.4A CN116734317A (en) | 2023-05-25 | 2023-05-25 | Method for exiting working condition of tripping heating system of main water supply pump under nuclear energy large-scale heating working condition |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN116734317A true CN116734317A (en) | 2023-09-12 |
Family
ID=87914309
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310599334.4A Pending CN116734317A (en) | 2023-05-25 | 2023-05-25 | Method for exiting working condition of tripping heating system of main water supply pump under nuclear energy large-scale heating working condition |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN116734317A (en) |
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2023
- 2023-05-25 CN CN202310599334.4A patent/CN116734317A/en active Pending
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