CN114412597A - Multi-steam-source auxiliary steam system of nuclear power unit and control method thereof - Google Patents
Multi-steam-source auxiliary steam system of nuclear power unit and control method thereof Download PDFInfo
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- 238000000034 method Methods 0.000 title claims abstract description 22
- 238000006243 chemical reaction Methods 0.000 claims abstract description 14
- 238000000605 extraction Methods 0.000 claims description 21
- 230000009467 reduction Effects 0.000 claims description 7
- 238000002955 isolation Methods 0.000 claims description 3
- 230000008569 process Effects 0.000 claims description 2
- 238000010248 power generation Methods 0.000 abstract description 10
- 230000008901 benefit Effects 0.000 abstract description 4
- 239000002826 coolant Substances 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 230000008859 change Effects 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 230000002596 correlated effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
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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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- 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
- F01K15/00—Adaptations of plants for special use
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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
- F01K17/00—Using steam or condensate extracted or exhausted from steam engine plant
- F01K17/04—Using steam or condensate extracted or exhausted from steam engine plant for specific purposes other than heating
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Abstract
The invention provides a multi-steam-source auxiliary steam system of a nuclear power unit and a control method thereof, wherein the system comprises a nuclear reaction unit, an auxiliary steam system, an external steam supply unit, a shaft seal steam system and a steam turbine; the nuclear reaction unit is respectively and independently connected with the auxiliary steam system, the shaft seal steam system and the steam turbine; the external steam supply unit is connected with the auxiliary steam system; the steam turbine is connected with the auxiliary steam system; the auxiliary steam system is connected with the shaft seal steam system. The invention supplies steam to the auxiliary steam system by using the low-grade extracted steam of the steam turbine, thereby improving the power generation efficiency and increasing the power generation benefit; the system and the control method thereof can improve the generating efficiency of the nuclear power unit and ensure the operation safety of the shaft seal system.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to a multi-steam-source auxiliary steam system of a nuclear power unit and a control method thereof.
Background
The nuclear energy plays an important role in the energy revolution, and the comprehensive utilization of the nuclear energy expands the nuclear energy from single power generation to multiple utilization modes, so that the nuclear energy is an important choice for the energy revolution and the low-carbon clean development. The normal reactor power is basically matched with the power of the generator, and the development of nuclear energy comprehensive utilization occupies part of the reactor thermal power, so that the generator cannot run at rated power, and therefore, the improvement of the secondary loop efficiency of the nuclear power unit becomes an important research subject.
The M310 reactor type nuclear power unit is provided with a steam converter system, the decompressed main steam is used as a primary side heating steam source of the steam converter system, and the secondary side of the steam converter system adopts demineralized water as a water source to generate low-pressure auxiliary steam at 1.2MPa and 188 ℃. The steam converter system is provided to isolate the auxiliary steam from direct contact with the secondary loop, preventing nuclear radioactive contamination. However, the failure rate of the steam converter system is high, and installation cost, operation cost and maintenance cost are increased.
At present, the steam grade of a nuclear/thermal power generating unit is high, and in order to increase the generating efficiency, the extracted steam of a high-pressure cylinder is used as a starting steam source of an auxiliary steam system. In addition, the VVER nuclear power unit can use high-pressure cylinder extraction steam as a starting steam source of the auxiliary steam system because of high-pressure cylinder extraction steam quality, but cannot meet the grade requirement of shaft seal steam during starting for nuclear power units such as AP1000, M310, EPR and the like because of low high-pressure cylinder extraction steam quality, so the steam source of the auxiliary steam system mainly uses steam obtained after main steam is decompressed as a main steam source of the auxiliary steam system.
Because the steam source of the auxiliary steam system is simultaneously used as the steam source of the shaft seal steam system, the steam source of the auxiliary steam system needs to be comprehensively transformed, the heat economy and the power generation efficiency of the nuclear power unit are improved, and the power generation amount of the nuclear power unit is increased.
Disclosure of Invention
The invention aims to provide a multi-steam-source auxiliary steam system of a nuclear power unit and a control method thereof, which can improve the power generation efficiency of the nuclear power unit and ensure the operation safety of a shaft seal system.
In order to achieve the purpose, the invention adopts the following technical scheme:
the invention provides a multi-steam-source auxiliary steam system of a nuclear power unit, which comprises a nuclear reaction unit, an auxiliary steam system, an external steam supply unit, a shaft seal steam system and a steam turbine, wherein the nuclear reaction unit is connected with the auxiliary steam system;
the nuclear reaction unit is respectively and independently connected with the auxiliary steam system, the shaft seal steam system and the steam turbine;
the external steam supply unit is connected with the auxiliary steam system;
the steam turbine is connected with the auxiliary steam system;
the auxiliary steam system is connected with the shaft seal steam system.
In the invention, the low-grade steam extraction of the steam turbine is utilized to supply steam to the auxiliary steam system, so that the power generation efficiency is improved, and the power generation benefit is increased; the low-grade steam extraction of the steam turbine is used as the steam source of the auxiliary steam system, the design is simple, the required equipment is less, and the nuclear power unit is convenient to change and reform.
In the invention, the multi-steam-source auxiliary steam system can be suitable for AP1000, M310, EPR and other nuclear power units.
As a preferred embodiment of the present invention, the nuclear reaction unit includes a driving device, a nuclear reactor, and a steam generating device, which are connected in this order.
Preferably, the steam outlet of the steam generating device is divided into three branches, and the three branches are respectively and independently connected with the auxiliary steam system, the shaft seal steam system and the steam turbine.
In the invention, the secondary side of the steam generating device is respectively and independently connected with the auxiliary steam system, the shaft seal steam system and the steam turbine.
As a preferred technical solution of the present invention, a valve group is provided on a pipeline between the steam turbine and the auxiliary steam system.
Preferably, the valve set comprises an electric valve, a check valve and an isolation valve which are connected in sequence by a steam flow direction.
As a preferable technical scheme of the invention, the external supply steam unit comprises an auxiliary steam system and an auxiliary boiler of an adjacent unit.
According to a preferred technical scheme of the invention, the steam source of the auxiliary steam system comprises steam decompressed by the steam generating device, externally supplied steam unit steam and steam of low-grade extraction steam of the steam turbine passing through a valve group.
Preferably, the steam source of the shaft seal steam system comprises steam decompressed by the steam generating device and auxiliary steam system steam.
The invention also provides a control method of the multi-steam-source auxiliary steam system of the nuclear power unit, which utilizes the system and specifically comprises the following steps: during the startup period of the nuclear power unit, the external steam supply unit provides steam for the auxiliary steam system, and the auxiliary steam system provides steam for the shaft seal steam system.
As a preferable aspect of the present invention, the control method further includes: in the starting process of the nuclear power unit, heat generated by a nuclear reaction unit is transferred to a steam generating device, when the steam amount generated by the steam generating device meets the steam supply requirements of a shaft seal steam system and an auxiliary steam system, a steam source of the shaft seal steam system is switched to steam decompressed by the steam generating device through the auxiliary steam system, and a steam source of the auxiliary steam system is switched to the steam decompressed by the steam generating device through an external steam supply unit.
In the invention, a coolant uses a driving device as a driving force to pass through a nuclear reactor, heat generated by the nuclear reactor is transferred to a steam generating device, and when the average temperature of a primary loop coolant is more than or equal to 292 ℃, a steam source of a shaft seal steam system is switched to steam decompressed by the steam generating device through an auxiliary steam system; when the power of the nuclear reactor is more than 5%, the steam source of the auxiliary steam system is switched to the steam decompressed by the steam generating device through the external steam supply unit.
As a preferable aspect of the present invention, the control method further includes: when the steam turbine operates and the pressure of the low-grade steam extraction point of the steam turbine is greater than the minimum allowable pressure of the auxiliary steam system, the steam source of the auxiliary steam system is switched to the steam of the low-grade steam extraction of the steam turbine passing through the valve group from the steam after being decompressed by the steam generating device.
In the invention, for an AP1000 nuclear power unit, the pressure of the auxiliary steam system is 0.8-1.2Mpa, and when the pressure of the low-grade steam extraction point of a steam turbine is more than 0.8MPa, the steam source of the auxiliary steam system is switched from the steam decompressed by the steam generating device to the steam of the low-grade steam extraction of the steam turbine passing through a valve group; during the normal operation of the nuclear power unit, the steam of the low-grade steam extraction of the steam turbine passing through the valve group is used for providing a steam source for the auxiliary steam system, so that the benefit can be improved.
As a preferred embodiment of the present invention, when the steam turbine is stopped, the steam source of the auxiliary steam system is switched from the low-grade steam extracted by the steam turbine to the steam decompressed by the steam generating device or the external steam supply unit through the steam of the valve group.
In the invention, after the steam turbine is stopped, the auxiliary steam system needs to be switched to the steam after the pressure reduction of the steam generating device or the external steam supply unit as a steam source; the power of the nuclear reactor is also maintained at 12% -14%, the supply of a shaft seal steam system is not affected, and the vacuum damage of a condenser caused by the loss of shaft seal steam is avoided.
As a preferable aspect of the present invention, the control method further includes: when the nuclear reactor is shut down, the decay heat of the nuclear reactor or the heat generated by the driving device is transferred to the steam generating device, the steam after the pressure reduction of the steam generating device provides steam for the shaft seal steam system, the steam source of the auxiliary steam system is switched to the external steam supply unit through the steam of the valve group by the low-grade extraction steam of the steam turbine, and the steam source of the auxiliary steam system is used as a standby steam source of the shaft seal steam system.
According to the invention, the decay heat of the nuclear reactor or the heat generated by the driving device (operation) is transferred to the steam generating device, when the steam amount generated by the steam generating device meets the steam supply requirement of the shaft seal steam system, the steam after the pressure reduction of the steam generating device continues to provide a steam source for the shaft seal steam system, and meanwhile, enough time is provided for switching the auxiliary steam system into an external steam supply unit as a standby steam source of the shaft seal steam system.
In the invention, when the decay heat of the nuclear reactor is reduced or the driving device is stopped, and the steam quantity generated by the steam generating device can not meet the steam supply requirement of the shaft seal steam system, the auxiliary steam system meeting the grade requirement of the shaft seal steam system supplies steam to the shaft seal steam system, thereby avoiding the influence on the shaft seal steam system due to vacuum damage, and avoiding the loss of the vacuum of the condenser so as to prolong the time for vacuumizing the condenser and starting the two loops.
Compared with the prior art, the invention has the following beneficial effects:
(1) according to the multi-steam-source auxiliary steam system of the nuclear power unit and the control method thereof, steam is supplied to the auxiliary steam system by using the low-grade extracted steam of the steam turbine, so that the power generation efficiency is improved, the power generation benefit is increased, the design is simple, the required equipment is less, and the change and the modification are convenient;
(2) according to the multi-steam-source auxiliary steam system of the nuclear power unit and the control method thereof, the safe and stable starting and operation of the nuclear power unit are ensured by setting and adopting a proper operation mode.
Drawings
FIG. 1 is a schematic structural diagram of a multi-steam-source auxiliary steam system of a nuclear power generating unit provided in embodiment 1 of the present invention;
FIG. 2 is a graph showing the trend of decay heat after a nuclear reactor is shut down for 1s according to example 4 of the present invention;
the system comprises a driving device 1, a nuclear reactor 2, a steam generating device 3, a steam turbine 4, an auxiliary steam system 5, a shaft seal steam system 6, an external steam supply unit 7 and a valve group 8.
Detailed Description
The technical solution of the present invention is further explained by the following embodiments. It should be understood by those skilled in the art that the examples are only for the understanding of the present invention and should not be construed as the specific limitations of the present invention.
Example 1
The embodiment provides a multi-steam-source auxiliary steam system of a nuclear power generating unit, and as shown in fig. 1, the system comprises a nuclear reaction unit, an auxiliary steam system 5, an external steam supply unit 7, a shaft seal steam system 6 and a steam turbine 4;
the nuclear reaction unit comprises a driving device 1, a nuclear reactor 2 and a steam generating device 3 which are connected in sequence; the secondary side of the steam generating device 3 is respectively and independently connected with an auxiliary steam system 5, a shaft seal steam system 6 and a steam turbine 4;
the external steam supply unit 7 is connected with the auxiliary steam system 5; the steam turbine 4 is connected with an auxiliary steam system 5; the auxiliary steam system 5 is connected with the shaft seal steam system 6;
a valve group 8 is arranged on a pipeline between the steam turbine 4 and the auxiliary steam system 5; the valve group 8 comprises an electric valve, a check valve and an isolation valve which are sequentially connected from the steam flow direction;
the external steam supply unit 7 comprises an auxiliary steam system and an auxiliary boiler of an adjacent unit;
the steam source of the auxiliary steam system 5 comprises steam decompressed by the steam generating device 3, steam of an external steam supply unit 7 and steam of a low-grade extraction steam of the steam turbine 4 passing through a valve group; the steam source of the shaft seal steam system 6 comprises steam decompressed by the steam generating device 3 and steam of the auxiliary steam system 5.
Example 2
The embodiment provides a control method of an AP1000 nuclear power unit multi-steam-source auxiliary steam system, which comprises the following steps:
during the startup of the nuclear power unit, the external steam supply unit provides steam for the auxiliary steam system, and the auxiliary steam system provides steam for the shaft seal steam system;
after a nuclear power unit is started, a coolant drives a nuclear reactor to react by using a driving device, heat generated by the reaction is transferred to a steam generating device, and when the average temperature of a primary loop coolant is 292 ℃, a steam source of a shaft seal steam system is switched to steam decompressed by the steam generating device from the auxiliary steam system; when the power of the nuclear reactor reaches 6%, switching a steam source of the auxiliary steam system from the external steam supply unit to steam decompressed by the steam generating device;
when the pressure of the low-grade steam extraction point of the steam turbine is greater than 0.8MPa, the steam source of the auxiliary steam system is switched to the steam of the low-grade steam extraction of the steam turbine through a valve group from the steam after the pressure of the steam generating device is reduced.
Example 3
The present embodiment is different from embodiment 2 in that, when the steam turbine is stopped, the steam source of the auxiliary steam system is switched from the steam extracted from the low-grade steam of the steam turbine through the valve group to the steam decompressed by the steam generating device or the external steam supply unit, and the rest is the same as embodiment 2.
Example 4
The difference between this embodiment and embodiment 2 is that when the nuclear reactor is shut down and the driving device is operated, the decay heat of the nuclear reactor or the heat generated by the driving device is transferred to the steam generating device, the steam after the pressure reduction of the steam generating device continues to provide steam for the shaft seal steam system, the steam source of the auxiliary steam system is switched to the external steam supply unit from the steam of the low-grade steam extraction of the steam turbine through the valve group, and the steam source of the auxiliary steam system is used as the backup steam source of the shaft seal steam system, which is otherwise the same as embodiment 2.
The influence of the shutdown of the AP1000 nuclear power unit on the steam after the pressure reduction of the steam generating device is taken as an example, the AP1000 nuclear power unit is in shutdown in a total operation 374 equivalent to a full-power day, and when the shutdown time reaches 35 hours, the reactor core decay heat is about 168 MW. Under the condition of the thermal state zero power of the nuclear reactor, the heat and the heat dissipation loss generated by the operation of a 15MW driving device are not considered, and the method is characterized by comprising the following steps of:
in the above formula, msT/h for generating steam quantity;
Pdis the primary decay heat, Mw;
hsthe enthalpy value of the main steam is kJ/kg;
hwthe enthalpy value of the main feed water is kJ/kg.
The calculation shows that the steam flow of about 26.6t/h can be generated by using the decay heat of the nuclear reactor, and the decay heat of the nuclear reactor can meet the steam supply requirement of the nuclear reactor before reaching the critical point. The core decay heat trend over time after 1s of nuclear reactor shutdown is shown in FIG. 2.
The decay heat generated during shutdown at the beginning of life is significantly greater than the heat generated during or at the end of life for a short period of time (10 min) after shutdown of the nuclear reactor, with a 7% difference between the beginning and end of life. As the shutdown time increases, the magnitude of decay heat is positively correlated to the core run time. After the nuclear reactor is shut down, the main steam of the steam generating device is decompressed to meet the steam supply requirements of the auxiliary steam system and the shaft seal steam system in a period after the shutdown.
Example 5
The difference between the embodiment and the embodiment 2 is that when the nuclear reactor is shut down and the driving device is shut down, the steam source of the auxiliary steam system is supplied with steam by the external steam supply unit; when the steam quantity generated by the steam generating device cannot meet the steam supply requirement of the shaft seal steam system, the steam source of the shaft seal steam system is switched back to the auxiliary steam system by the steam decompressed by the steam generating device, so that the requirements of a user of the shaft seal steam supply and auxiliary steam system are met.
The applicant declares that the above description is only a specific embodiment of the present invention, but the scope of the present invention is not limited thereto, and it should be understood by those skilled in the art that any changes or substitutions that can be easily conceived by those skilled in the art within the technical scope of the present invention are within the scope and disclosure of the present invention.
Claims (10)
1. A multi-steam-source auxiliary steam system of a nuclear power unit is characterized by comprising a nuclear reaction unit, an auxiliary steam system, an external steam supply unit, a shaft seal steam system and a steam turbine;
the nuclear reaction unit is respectively and independently connected with the auxiliary steam system, the shaft seal steam system and the steam turbine;
the external steam supply unit is connected with the auxiliary steam system;
the steam turbine is connected with the auxiliary steam system;
the auxiliary steam system is connected with the shaft seal steam system.
2. The system of claim 1, wherein the nuclear reaction unit comprises a driving device, a nuclear reactor, and a steam generating device connected in series;
preferably, the steam outlet of the steam generating device is divided into three branches, and the three branches are respectively and independently connected with the auxiliary steam system, the shaft seal steam system and the steam turbine.
3. The system according to claim 1 or 2, wherein a valve group is arranged on a pipeline between the steam turbine and the auxiliary steam system;
preferably, the valve set comprises an electric valve, a check valve and an isolation valve which are connected in sequence by a steam flow direction.
4. A system according to any one of claims 1-3, wherein the external steam supply unit comprises an auxiliary steam system and an auxiliary boiler of an adjacent train.
5. The system according to any one of claims 1 to 4, wherein the steam source of the auxiliary steam system comprises steam decompressed by the steam generating device, externally supplied steam unit steam and steam of low-grade steam extraction of a steam turbine passing through a valve group;
preferably, the steam source of the shaft seal steam system comprises steam decompressed by the steam generating device and auxiliary steam system steam.
6. A control method of a multi-steam-source auxiliary steam system of a nuclear power unit is characterized in that the control method utilizes the system of any one of claims 1 to 5, and specifically comprises the following steps: during the startup period of the nuclear power unit, the external steam supply unit provides steam for the auxiliary steam system, and the auxiliary steam system provides steam for the shaft seal steam system.
7. The control method according to claim 6, characterized by further comprising: in the starting process of the nuclear power unit, heat generated by a nuclear reaction unit is transferred to a steam generating device, when the steam amount generated by the steam generating device meets the steam supply requirements of a shaft seal steam system and an auxiliary steam system, a steam source of the shaft seal steam system is switched to steam decompressed by the steam generating device through the auxiliary steam system, and a steam source of the auxiliary steam system is switched to the steam decompressed by the steam generating device through an external steam supply unit.
8. The control method according to claim 6 or 7, characterized by further comprising: when the steam turbine operates and the pressure of the low-grade steam extraction point of the steam turbine is greater than the minimum allowable pressure of the auxiliary steam system, the steam source of the auxiliary steam system is switched to the steam of the low-grade steam extraction of the steam turbine passing through the valve group from the steam after being decompressed by the steam generating device.
9. The control method according to any one of claims 6 to 8, wherein when a steam turbine is stopped, a steam source of the auxiliary steam system is switched from the steam of the low-grade extraction steam of the steam turbine through a valve group to the steam after the pressure reduction of the steam generating device or the external supply steam unit.
10. The control method according to any one of claims 6 to 9, characterized by further comprising: when the nuclear reactor is shut down, the decay heat of the nuclear reactor or the heat generated by the driving device is transferred to the steam generating device, when the steam amount generated by the steam generating device meets the steam supply requirement of the shaft seal steam system, the steam after the pressure reduction of the steam generating device provides steam for the shaft seal steam system, the steam source of the auxiliary steam system is switched to the external steam supply unit through the steam of the valve group by the low-grade steam extraction of the steam turbine, and the steam source of the auxiliary steam system is used as a standby steam source of the shaft seal steam system.
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