CN113530613B - Control method after gas loss of conventional island of nuclear power plant - Google Patents
Control method after gas loss of conventional island of nuclear power plant Download PDFInfo
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- CN113530613B CN113530613B CN202110699007.7A CN202110699007A CN113530613B CN 113530613 B CN113530613 B CN 113530613B CN 202110699007 A CN202110699007 A CN 202110699007A CN 113530613 B CN113530613 B CN 113530613B
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- condenser
- conventional island
- steam
- power plant
- nuclear power
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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
- F01D11/00—Preventing or minimising internal leakage of working-fluid, e.g. between stages
- F01D11/02—Preventing or minimising internal leakage of working-fluid, e.g. between stages by non-contact sealings, e.g. of labyrinth type
- F01D11/04—Preventing or minimising internal leakage of working-fluid, e.g. between stages by non-contact sealings, e.g. of labyrinth type using sealing fluid, e.g. steam
- F01D11/06—Control thereof
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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
- F01K9/00—Plants characterised by condensers arranged or modified to co-operate with the engines
- F01K9/003—Plants characterised by condensers arranged or modified to co-operate with the engines condenser cooling circuits
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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
- F01K9/00—Plants characterised by condensers arranged or modified to co-operate with the engines
- F01K9/006—Vacuum-breakers
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28B—STEAM OR VAPOUR CONDENSERS
- F28B11/00—Controlling arrangements with features specially adapted for condensers
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Abstract
The invention discloses a control method after the conventional island of a nuclear power plant loses gas, which comprises the following steps: 1) Immediately after the conventional island loses gas, the shaft seal steam inlet valve is manually adjusted on site, and the CET shaft seal pressure is maintained; 2) After high-temperature steam and drainage entering the condenser are isolated, the CVI system is shut down, and a vacuum breaking valve is opened; 3) And after the condenser pressure is restored to the atmospheric pressure, the CET system is exited. Compared with the prior art, the control method for the conventional island of the nuclear power plant after the gas loss can maintain the vacuum of the condenser as far as possible so as to isolate high-temperature steam and drainage water entering the condenser for a sufficient time, and meanwhile, equipment damage and personnel scalding caused by shaft seal steam leakage are avoided.
Description
Technical Field
The invention relates to the field of debugging of nuclear power plants, in particular to a control method after gas loss of a conventional island of a nuclear power plant.
Background
EPR (European Pressurized Water Reactor ) units have great difference in valve power selection from CPR (China Pressurized Water Reactor ) units, and nuclear island areas basically adopt electric valves, while conventional island areas largely adopt pneumatic valves. Aiming at the influence on the system and the unit after the pneumatic valve loses the gas and the transient control strategy, the CPR unit is not verified by the whole gas loss test, and the EPR unit adopts the COC107 test for the first time to make up for the part of blank.
The COC107 (loss of compressed air for instrument) is a simulation of loss of SAR (Instrument compressed air distribution system, compressed air distribution system for instrument) under the conventional island hot vacuuming condition, verifies the correct action condition of each system and equipment and the feasibility of a transient control strategy, provides reference and reference for emergency intervention after the occurrence of the transient condition of loss of air during the normal operation of the subsequent unit, in the conventional test scheme, the actual loss of air is realized by closing a main valve on an air inlet main pipe of the conventional island, the transient control strategy of the system after the loss of air of the conventional island is as shown in fig. 1, the sequence is CVI-CET-SVA-ADG-CEX-CRF-AAD-APA-other system, wherein CVI (Condenser vacuum system) is a condenser vacuum system, CET (Turbine gland seal system) is a steam engine shaft sealing system, SVA (Auxiliary steam distribution system) is an auxiliary steam distribution system, ADG (Feed water tank and gas stripper system) is a feed-water deaerator system, CEX (Condensate extraction system) is a condensate extraction system, CRF (Circulating water system) is a circulating water system, AAD (Start up and shut down feed water system) is a start-up and shut-down water supply system, and APA (Main feed water pump system) is an electric main water supply pump system.
However, the transient control strategy is unreasonable to influence the safe operation of major equipment by combining the analysis of influences on aspects such as a main machine equipment, a cold source equipment, a water supply equipment and the like after the gas loss, and at least has the following risks on the major equipment such as a steam turbine, a condenser, a deaerator, a water supply pump and the like:
1) The shaft seal CET system intervenes too late. After SAR is lost, a CET steam inlet valve of a shaft seal system of the steam turbine is fully opened, and when an adjusting function is unavailable, the overpressure of shaft seal steam can be caused to leak. The transient control strategy is to intervene the CET system after the CVI vacuum pump is stopped and the condenser pressure of the vacuum breaking valve is opened to be increased to the atmospheric pressure, so that the shaft seal steam of the CET system leaks out in long-time overpressure, and the risks of damage to equipment such as a turbine bearing and personnel scalding exist.
2) The steam and the drainage entering the condenser interfere too late. After SAR is lost, the siphon breaking valve of the CRF system is opened in a gas loss way, the CRF pump cannot run for a long time, the vacuum of the condenser cannot be maintained, and the usability of the condenser is affected. The high-temperature steam of the ADG system and the high-temperature steam of the VPU system (Main steam system) of the transient control strategy are continuously discharged into the condenser after the vacuum of the condenser is broken, so that the temperature and the pressure of the condenser are continuously increased, and the risk of damaging a titanium pipe of the condenser and a low-pressure cylinder burst disk of a steam turbine exists.
3) ADG backwaters to a condenser isolation valve and an APA/AAD pump intervenes too late. After SAR is lost, under the condition that a CEX valve station regulating valve and an ADG steam inlet regulating valve are closed when the air is lost, the ADG loses water inlet and steam inlet, the liquid level and the pressure of the deaerator are continuously reduced, the safe operation of the APA/AAD pump and the water supply of the steam generator are affected, and at the moment, the risks of cavitation and vibration damage are greatly increased due to long-time operation of the APA/AAD pump.
In view of the foregoing, it is desirable to provide a control method after loss of gas in a conventional island of a nuclear power plant that overcomes the above-described problems.
Disclosure of Invention
The invention aims at: the control method for the conventional island of the nuclear power plant after the gas loss is provided, and the safe operation of important equipment and personnel safety of the nuclear power plant are effectively ensured.
In order to achieve the above purpose, the invention provides a control method after the conventional island of a nuclear power plant loses gas, which comprises the following steps:
1) Immediately after the conventional island loses gas, the shaft seal steam inlet valve is manually adjusted on site, and the CET shaft seal pressure is maintained;
2) After high-temperature steam and drainage entering the condenser are isolated, the CVI system is shut down, and a vacuum breaking valve is opened;
3) And after the condenser pressure is restored to the atmospheric pressure, the CET system is exited.
As a preferred embodiment of the control method after the conventional island of the nuclear power plant loses gas, the step 3) further comprises the step of stopping the SVA system after exiting the CET system.
As a preferred implementation mode of the control method after the conventional island of the nuclear power plant loses gas, in the step 1), a shaft seal steam inlet valve is manually adjusted, and high-temperature steam entering a condenser needs to be isolated from water drainage as soon as possible during the period of maintaining CET shaft seal pressure.
As a preferred implementation mode of the control method after the conventional island of the nuclear power plant loses gas, the isolation of high-temperature steam and drainage entering the condenser comprises the steps of cutting the exhaust steam of the ADG from the condenser to the atmosphere, isolating backwater from the ADG deaerator to the condenser, and avoiding a large amount of high-temperature steam entering the condenser.
As a preferred implementation mode of the control method after the conventional island of the nuclear power plant loses gas, the method for isolating high-temperature steam entering the condenser from water drainage further comprises the step of closing the VPU system to drain water from the condenser.
As a preferred implementation mode of the control method after the conventional island of the nuclear power plant loses gas, the step 3) further comprises a step 4) of stopping the CRF pump after isolating all heat sources entering the condenser, so that the CRF pump is prevented from running for a long time under the working condition that the siphon break valve is opened.
As a preferred implementation mode of the control method after the conventional island of the nuclear power plant loses gas, the control method further comprises a step 5) of stopping the APA and the AAD pump after isolating backwater from the ADG deaerator to the condenser.
As a preferred implementation mode of the control method after the conventional island of the nuclear power plant loses gas, the step 5) gradually stops the operation of the CEX pump after the APA pump and the AAD pump are stopped.
As a preferred embodiment of the control method after the conventional island of the nuclear power plant loses gas, the step 5) further comprises a step 6) of stopping the ADG.
As a preferred embodiment of the control method after the conventional island of the nuclear power plant loses gas, the step 5) and the step 6) are carried out in parallel with the step 3) and the step 4) after the step 2).
As a preferred implementation mode of the control method after the conventional island of the nuclear power plant loses gas, the control method further comprises a step 7), after the step 4) and the step 6) are completed, other systems are checked and operated, and the other systems comprise an ABP system, an AHP system, an SEK system, an SIR system and a GSS system.
Drawings
The following describes the control method after the conventional island of the nuclear power plant loses the gas and the beneficial effects thereof in detail by combining the attached drawings and the specific embodiments.
FIG. 1 is a schematic diagram of a conventional island post-loss transient control strategy.
FIG. 2 is a schematic diagram of a conventional island out-of-gas phase system for a nuclear power plant.
FIG. 3 is a flow chart of a control method after the conventional island of the nuclear power plant loses gas.
Detailed Description
In order to make the objects, technical solutions and advantageous technical effects of the present invention clearer, the present invention will be further described in detail with reference to the accompanying drawings and detailed description. It should be understood that the detailed description is presented herein for purposes of illustration only and is not intended to limit the invention.
Referring to fig. 2 and 3, in order to solve the problems in the transient control strategy of the system after the conventional island loses gas, the inventor analyzes each risk point by carding the state and the influence of each system after losing gas, and optimizes and improves the control strategy from the aspect of ensuring the safe withdrawal of the system equipment by taking the main risk point as traction. The method specifically comprises the following steps:
1) Control strategy optimization after loss of gas in host device
After the conventional island loses gas, the CET shaft seal pressure regulating function is not available, but the turbine lubricating oil and the jigger system still normally operate, and the CET system can be continuously put into use. In order to maintain the vacuum of the condenser as much as possible so as to have enough time for isolating high-temperature steam and drainage entering the condenser, and simultaneously avoid equipment damage and personnel scalding caused by leakage of shaft seal steam, a shaft seal steam inlet valve is required to be manually controlled on site immediately to maintain CET shaft seal pressure, then a CVI system is stopped after the high-temperature steam and drainage entering the condenser are isolated, a vacuum breaking valve is opened, and the CET system is exited after the pressure of the condenser is restored to the atmospheric pressure.
2) Control strategy optimization after loss of gas of cold source equipment
During manual adjustment of the CET shaft seal pressure, high temperature steam entering the condenser and water drain are isolated as soon as possible in order to prevent damage to the condenser and low pressure cylinder equipment, as the CRF cannot operate for long periods of time to maintain the condenser vacuum. According to the influence degree on the condenser, the exhaust steam of the ADG is preferentially cut to the atmosphere from the condenser, the deaerator is isolated from backwater of the condenser, and a large amount of high-temperature steam of the deaerator is prevented from entering the condenser.
After isolating all heat sources entering the condenser, the CRF pump is stopped, and the CRF pump is prevented from running for a long time under the working condition that the siphon break valve is opened.
3) Control strategy optimization after water supply equipment loses gas
After the conventional island loses gas, a CEX valve station regulating valve and a deaerator main and auxiliary steam inlet regulating valve are closed, and the deaerator can not maintain water level and pressure. On the other hand, after the APA pump is started by the gas loss signal, the APA pump and the AAD pump are operated under the working condition of small flow. In order to prevent damage caused by cavitation and excessive vibration of the APA/AAD pump due to the reduction of the water level and the pressure of the deaerator, the backwater from the ADG to the condenser should be timely isolated, the APA and the AAD pump are stopped, and the CEX pump is gradually withdrawn from operation.
Through the above analysis, a conventional island out-of-gas control method as shown in fig. 3 was obtained.
The control method after the conventional island of the nuclear power plant loses gas comprises the following steps:
and S1, immediately after the conventional island loses gas, manually adjusting a shaft seal steam inlet valve on site, and maintaining CET shaft seal pressure.
During manual adjustment of the shaft seal steam inlet valve and maintenance of CET shaft seal pressure, high-temperature steam entering the condenser needs to be isolated as soon as possible and water is drained: the method comprises the steps of cutting exhaust steam of the ADG to the atmosphere from the condenser, isolating backwater from the ADG deaerator to the condenser, avoiding a large amount of high-temperature steam of the deaerator from entering the condenser, and closing the VPU system to drain the condenser.
And S2, after high-temperature steam entering the condenser is isolated from drainage, the CVI system is shut down, and a vacuum breaking valve is opened.
And S3, after the condenser pressure is restored to the atmospheric pressure, the CET system is exited. This step also includes shutting down the SVA system after exiting the CET system.
And S4, after isolating all heat sources entering the condenser, stopping the CRF pump, and preventing the CRF pump from running for a long time under the working condition that the siphon break valve is opened.
S5, after isolating backwater from the ADG deaerator to the condenser, stopping the APA and the AAD pump, and gradually stopping the CEX pump; this step may be performed after step S2 in parallel with step S3.
And S6, stopping the ADG after the step S5 is completed.
And S7, after the step S4 and the step S6 are completed, checking and operating other systems including an ABP system (Low pressure feed water heater system, low-pressure feed water heater system), an AHP system (High pressure feed water heater system, high-pressure feed water heater system), an SEK system (Conventional island liquid waste collection system, conventional island waste liquid collection system), an SIR system (Chemical reagents injection system, chemical dosing system) and a GSS system (Moisture separator-separator system, steam-water separator-reheater system).
Compared with the prior art, the control method for the nuclear power plant after the conventional island loses gas has at least the following advantages:
1) According to the invention, after the conventional island loses gas, the shaft seal steam inlet valve is manually adjusted on site immediately to maintain CET shaft seal pressure, then the CVI system is stopped after high-temperature steam entering the condenser is isolated from drainage, the vacuum breaking valve is opened, and after the pressure of the condenser is restored to atmospheric pressure, the CET system is exited, so that the vacuum of the condenser can be maintained as much as possible to isolate the high-temperature steam entering the condenser from drainage in a sufficient time, and meanwhile, equipment damage and personnel scalding caused by the leakage of the shaft seal steam are avoided;
2) According to the invention, during the period of manually adjusting the shaft seal steam inlet valve and maintaining CET shaft seal pressure, the exhaust steam of the ADG is cut to the atmosphere from the condenser, the backwater from the ADG deaerator to the condenser is isolated, a large amount of high-temperature steam of the deaerator is prevented from entering the condenser, the VPU system is closed to drain the condenser, the high-temperature steam and the drainage entering the condenser are isolated as soon as possible, and the damage of the condenser and low-pressure cylinder equipment can be prevented; according to the invention, after isolating all heat sources entering the condenser, the CRF pump is stopped, so that the CRF pump is prevented from running for a long time under the working condition that the siphon break valve is opened;
3) According to the invention, after the conventional island loses gas, backwater from the ADG deaerator to the condenser is timely isolated, the APA and the AAD pump are stopped, and the CEX pump is gradually withdrawn from operation, so that damage caused by cavitation and overhigh vibration of the APA/AAD pump due to continuous reduction of the water level and the pressure of the deaerator is avoided.
Through practical verification, the state of the COC107 test unit adopting the control method after the conventional island of the nuclear power plant loses gas is safe and controllable, no safety quality event occurs, the construction period is reduced compared with a project, the safety quality is improved, and human errors are reduced.
In summary, the control method for the conventional island after the gas loss of the nuclear power plant eliminates risk factors in the transient control strategy of the system after the gas loss of the conventional island, can ensure the safety of conventional island systems and equipment such as a steam turbine, a condenser, an APA/AAD pump and the like, and effectively shortens the control time after the gas loss of the conventional island.
Modifications and variations of the above embodiments will be apparent to those skilled in the art in light of the above teachings. Therefore, the invention is not limited to the specific embodiments disclosed and described above, but some modifications and changes of the invention should be also included in the scope of the claims of the invention. In addition, although specific terms are used in the present specification, these terms are for convenience of description only and do not limit the present invention in any way.
Claims (6)
1. The control method after the conventional island of the nuclear power plant loses the gas is characterized by comprising the following steps of:
s1) immediately and manually adjusting a shaft seal steam inlet valve on site after the conventional island loses gas, and maintaining the shaft seal pressure of a shaft seal system of the steam turbine;
s2) after high-temperature steam entering the condenser is isolated from drainage, the condenser vacuum system is stopped, and a vacuum breaking valve is opened;
s3) after the condenser pressure is restored to the atmospheric pressure, exiting the turbine sealing system;
s4) after isolating all high-temperature steam entering the condenser, stopping the circulating water system pump;
s5) after isolating backwater from the deaerator of the feed water degassing system to the condenser, stopping the electric main feed water pump system, starting and stopping the feed water system pump, and gradually stopping the condensed water pumping system pump;
s6) after the step S5 is completed, the water supply and gas removal system is stopped;
s7) after the step S4 and the step S6 are completed, checking and operating other systems including a low-pressure feed water heater system, a high-pressure feed water heater system, a conventional island waste liquid collecting system, a chemical dosing system and a steam-water separation reheater system are carried out.
2. The control method after the gas loss of the conventional island of the nuclear power plant according to claim 1, wherein the method comprises the following steps of: the step 3) further includes disabling the auxiliary steam distribution system after exiting the steam turbine seal system.
3. The control method after the gas loss of the conventional island of the nuclear power plant according to claim 1 or 2, characterized in that: in step 1), the shaft seal steam inlet valve is manually adjusted, and high-temperature steam entering the condenser needs to be isolated from drainage as soon as possible during the period of maintaining the shaft seal pressure of the steam turbine shaft seal.
4. A method of controlling a nuclear power plant after loss of gas in a conventional island according to claim 3, wherein: the high-temperature steam and drainage of the water supply and degassing system are isolated by cutting the exhaust steam of the water supply and degassing system from the condenser to the atmosphere, and backwater from the deaerator of the water supply and degassing system to the condenser is isolated, so that a large amount of high-temperature steam of the deaerator is prevented from entering the condenser.
5. The control method after the gas loss of the conventional island of the nuclear power plant according to claim 4, wherein the method comprises the following steps of: the isolation of high temperature steam entering the condenser and drainage also comprises closing the drainage from the conventional island main steam system to the condenser.
6. The control method after the gas loss of the conventional island of the nuclear power plant according to claim 1, wherein the method comprises the following steps of: the step 5) and the step 6) are performed in parallel with the step 3) and the step 4) after the step 2).
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| Publication number | Priority date | Publication date | Assignee | Title |
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| JPH06281367A (en) * | 1993-03-26 | 1994-10-07 | Toshiba Corp | Vacuum keeping system for condenser |
| EP2801703A1 (en) * | 2013-05-08 | 2014-11-12 | Siemens Aktiengesellschaft | Steam turbine plant with sealing steam line |
| CN104791022B (en) * | 2015-02-15 | 2016-06-22 | 华北电力科学研究院有限责任公司 | Gas power station axle envelope and vacuum system and on off control method thereof |
| CN105781631B (en) * | 2016-05-10 | 2017-11-03 | 中国能源建设集团山西省电力勘测设计院有限公司 | A kind of coal-fired power plant's steam turbine red switch activation system and its startup method |
| CN110542325B (en) * | 2019-09-26 | 2021-03-02 | 岭澳核电有限公司 | Condenser vacuum system of nuclear power station |
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