CN111486438A - Control method for preventing overflow of steam generator caused by auxiliary water supply system - Google Patents
Control method for preventing overflow of steam generator caused by auxiliary water supply system Download PDFInfo
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- CN111486438A CN111486438A CN202010190136.9A CN202010190136A CN111486438A CN 111486438 A CN111486438 A CN 111486438A CN 202010190136 A CN202010190136 A CN 202010190136A CN 111486438 A CN111486438 A CN 111486438A
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- water supply
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
- F22D5/00—Controlling water feed or water level; Automatic water feeding or water-level regulators
- F22D5/26—Automatic feed-control systems
- F22D5/34—Applications of valves
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/42—Applications, arrangements, or dispositions of alarm or automatic safety devices
- F22B37/46—Applications, arrangements, or dispositions of alarm or automatic safety devices responsive to low or high water level, e.g. for checking, suppressing, extinguishing combustion in boilers
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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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
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- General Engineering & Computer Science (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Emergency Management (AREA)
- Business, Economics & Management (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Control Of Non-Electrical Variables (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to a control method for preventing an auxiliary water supply system from causing overflow of a steam generator, which is characterized in that corresponding regulating valves are configured for water supply isolation and regulation functions according to the process characteristics of pipeline collection of feed pumps in an A row and a B row of the auxiliary water supply system. After the auxiliary water supply system is put into operation, when the liquid level of the steam generator reaches a high liquid level, the two electromagnetic valves of the A row and the B row configured by the auxiliary water supply regulating valve are electrified through automatic interlocking control, and the auxiliary water supply regulating valve is closed and the water supply to the steam generator is cut off given an instruction of 0% opening of the regulating valve. If the operator judges that the steam generator needs to be supplemented with water along with the progress of the working condition, the control of the regulating valve can be manually switched to a manual regulating mode, and the regulating valve is regulated to a proper opening degree from the 0% opening degree to supplement water. The invention reduces the potential risk of overflow of the steam generator in the operation process of the nuclear power station, and improves the effectiveness of the control of the auxiliary water supply system and the safety level of the operation of the power station.
Description
Technical Field
The invention belongs to the automatic control technology of nuclear power stations, and particularly relates to a control method for preventing an auxiliary water supply system from causing overflow of a steam generator.
Background
The auxiliary water supply system is an important safety special system in a pressurized water reactor nuclear power station. After the steam generator loses main water supply or secondary water supply of starting water supply, water is supplied to the steam generator to discharge the waste heat of the reactor core. The system is provided with 2 electric pumps, 2 steam-driven pumps and 6 auxiliary water supply flow regulating valves, and each regulating valve is provided with two electromagnetic valves belonging to a row A and a row B respectively. The flow of the 2 electric pumps is converged and then divided into 3 paths, and water is supplemented to the 3 steam generators through the 3 regulating valves; after the flow of the 2 steam-driven pumps is converged, the flow is divided into 3 paths to supplement water for the same 3 steam generators through other 3 regulating valves. The water supplemented by the electric pump and the steam driven pump of each steam generator is converged into a water supply pipeline after corresponding two regulating valves and is connected to the steam generator, as shown in figure 1.
In the design of the prior nuclear power plant, the auxiliary water supply system has the following characteristics:
the fault position of the auxiliary water supply flow regulating valve is a full open position. Each auxiliary water supply flow regulating valve is provided with two electromagnetic valves which are connected in series and are respectively supplied with power and controlled by the A row and the B row, and as shown in the attached figure 1, when any row of the electromagnetic valves is powered off, the auxiliary water supply flow regulating valve can be fully opened. The valves are in the modulating mode only when the A and B banks of solenoid valves are energized simultaneously. After the auxiliary water supply is started, because the water supply amount is sufficient, an operator must monitor the water level of the steam generator all the time, when the water level of the steam generator is too high, the electromagnetic valves of the A row and the B row need to be electrified manually, then the opening of the valve is manually adjusted, and the proper water supplement amount of the steam generator is ensured. When a steam heat transfer pipe rupture accident (SGTR) occurs, due to the urgency and unpredictability of the accident, the water level of a steam generator can be caused to be too high in a short time, an operator is busy in handling emergency, the water level of the steam generator is observed and the opening of a regulating valve is tracked and adjusted in a flawless manner, the steam generator is overflowed, radioactive pollution plants and other equipment carried by overflowed media are caused, and power station damage and economic loss are caused.
Chinese patent 201310394890.4 discloses a "safety replenishment method for auxiliary water supply system" (publication No. CN103474108B), which divides six regulating valves corresponding to three steam generators into two groups, i.e., a column a and a column B, wherein three regulating valves are powered by a power supply sequence of the column a, and the other three regulating valves are powered by a power supply sequence of the column B; and meanwhile, the corresponding auxiliary water supply electric pump and the steam driven pump are respectively controlled and powered by the A row and the B row. The adjusting signal of the adjusting valve is closed-loop controlled by the corresponding liquid level signal of the steam generator to control the opening of the adjusting valve to realize the automatic adjusting function. The technical scheme of the patent is simple relatively, and A row and B row are completely independent, and the governing valve only disposes a single solenoid valve, and control function's realization is easier relatively. The patent is not suitable for a control scheme that the regulating valve is provided with two electromagnetic valves of the A line and the B line, and cannot realize the function of cross control on the flow of the feed water pumps of the A line and the B line simultaneously.
Disclosure of Invention
The invention aims to provide a control method for preventing an auxiliary water supply system from causing overflow of a steam generator aiming at the requirement of safety design of a nuclear power station.
The technical scheme of the invention is as follows: a control method for preventing an auxiliary water supply system from causing overflow of a steam generator is characterized in that aiming at the auxiliary water supply system of which an A-row auxiliary water supply pump and a B-row auxiliary water supply pump are converged to form a water supply line, regulating valves which are provided with two electromagnetic valves respectively supplied with power by the A-row auxiliary water supply pump and the B-row auxiliary water supply pump and are arranged on the water supply line are controlled, after any row of auxiliary water supply pumps are started, the corresponding regulating valves are automatically and interlocked to supply water, when the water supply amount is too much and the A-row auxiliary water supply pump and the B-row auxiliary water supply pump simultaneously detect high signals of the liquid level of the steam generator, the two electromagnetic valves which are provided with the auxiliary water supply flow regulating valves and are respectively supplied with power by the A-row auxiliary water supply flow regulating valves and the.
Further, according to the control method for preventing the auxiliary water supply system from causing the overflow of the steam generator, the auxiliary water supply pump includes two electric pumps respectively belonging to the row a and the row B and two steam-driven pumps respectively belonging to the row a and the row B, and when any one auxiliary water supply pump (electric pump or steam-driven pump) is started and a high liquid level signal of the steam generator corresponding to the pump is detected, the electromagnetic valve of the row where the trigger signal is located is electrified to enter a preparation isolation state.
Further, according to the control method for preventing the auxiliary water supply system from causing the overflow of the steam generator, when the high signal of the liquid level of the steam generator is not detected in any row, the electromagnetic valve of the corresponding row is in a power-off state, and the corresponding regulating valve is in an open state.
Further, in the control method for preventing the auxiliary water supply system from causing the overflow of the steam generator, the setting of the regulating valve with the 0% opening instruction to close the regulating valve means that two electromagnetic valves powered by the A column and the B column on a regulating valve gas circuit are electrified simultaneously, and the 0% opening instruction is triggered to adjust the air inflow to close the valves.
Further, according to the control method for preventing the auxiliary water supply system from causing the overflow of the steam generator, after the auxiliary water supply regulating valve is triggered to be automatically closed, no matter how the liquid level of the steam generator changes, the auxiliary water supply regulating valve is always in a closed state until an operator accurately judges the working condition and then manually takes the next step.
Furthermore, if the auxiliary water supply function is isolated by mistake when the SGTR accident of the steam generator is judged not to occur, an operator adjusts the regulating valve from 0% opening degree to a specified opening degree after switching the control mode of the regulating valve to a manual mode, and normal water supplement of the steam generator is ensured.
The invention has the following beneficial effects: aiming at the characteristic of bus convergence of the water feeding pumps in the A row and the B row, the invention realizes the isolation function of auxiliary water feeding by arranging the regulating valves of the electromagnetic valves in the A row and the B row, and the configuration can isolate the auxiliary water feeding when the working condition needs and can regulate the water feeding flow when necessary. When the SGTR accident occurs in the nuclear power station, the auxiliary water supply function can be automatically isolated, the steam generator is prevented from overflowing, the response time of an operator is prolonged, and the working condition is reasonably judged. The valve may be adjusted to the proper opening by a manual function if operator analysis does not require isolation of the auxiliary feed water. The implementation of the method solves the potential risk of the auxiliary water supply function of the conventional nuclear power station, and improves the effectiveness of an auxiliary water supply system and the safety level of the operation of the nuclear power station. Compared with the prior art, the method realizes the cross control of the equipment in the A line and the equipment in the B line, the process flow is more complex, and the difficulty of the control realization is higher.
Drawings
FIG. 1 is a flow diagram of an auxiliary feedwater process of the present invention;
FIG. 2 is a schematic diagram of an implementation of the auxiliary feedwater flow isolation control of the present invention (electric pump section, steam driven pump or other drive pump alike).
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
The invention provides a control method for preventing an auxiliary water supply system from causing overflow of a steam generator, which is an auxiliary water supply system for converging water supply buses of a water supply pump in a row A and a water supply pump in a row B into a main pipe for supplying water. The structure of the system is shown in figure 1, the system is provided with 2 electric pumps, 2 steam-driven pumps and 6 auxiliary feed water flow regulating valves, and each regulating valve is provided with two electromagnetic valves which are connected in series and respectively belong to the A row and the B row (namely, the electromagnetic valves are respectively supplied with power and controlled by the A row and the B row). The flow of the 2 electric pumps is converged and then divided into 3 paths, and the 3 paths of the electric pumps are respectively used for replenishing water for the 3 steam generators through 3 regulating valves; the flow of 2 steam-driven pumps is converged and then divided into 3 paths, and the 3 paths are respectively used for replenishing water to 3 identical steam generators through 3 other regulating valves. The electric pump and the steam-driven pump of each steam generator are supplemented with water and are converged into a water supply pipeline to be connected to the steam generator after the two corresponding regulating valves are arranged.
After the auxiliary water supply system is put into operation, the control system automatically interlocks the electromagnetic valve of the auxiliary water supply regulating valve to be electrified according to a liquid level height signal of the steam generator, and simultaneously sends out an instruction of 0% opening of the regulating valve, closes the regulating valve and switches the water supply of the steam generator. According to the scheme, after any row of auxiliary water feeding pumps (electric pumps or steam-driven pumps) are started, the corresponding regulating valves are automatically opened in a linkage mode to replenish water, when the amount of water replenishing is excessive, and only when the rows A and B detect a high-level signal of a liquid level of a steam generator at the same time, two electromagnetic valves which are respectively powered by the rows A and B and are arranged on the auxiliary water feeding flow regulating valves are electrified through automatic interlocking, meanwhile, the regulating valves are closed by giving 0% opening instructions of the regulating valves, namely, the two electromagnetic valves which are powered by the rows A and B are closed at the same time. This design is in order to close the governing valve in time through automatic chain when steam generator's moisturizing is too much reaches high liquid level, stops the moisturizing, avoids causing adverse effect to other equipment.
Because each auxiliary water supply flow regulating valve is provided with two electromagnetic valves respectively supplied with power by the A row and the B row, when the auxiliary water supply pump of one row is started and a high liquid level signal of a steam generator occurs at the same time, the electromagnetic valve of the row is electrified, the regulating valve is not closed at the moment, the electromagnetic valve of the corresponding row is allowed to be electrified to enter a preparation isolation state, the electromagnetic valve of the other row is still in a power-off state, and the regulating valve is still opened. The purpose is that two all satisfy the isolation condition and just close the governing valve, avoid single rank false isolation signal to trigger the moisturizing isolation, influence the safety function of evaporimeter moisturizing. When the single-row electromagnetic valve is powered off due to any one row of faults, the regulating valve is fully opened, and the purpose is to enable the equipment to be in a safer position for a power plant when the equipment is in fault. Because the safety function of supplementary feedwater is for providing steam generator moisturizing, consequently makes the governing valve open when equipment trouble, moisturizing when not influencing the operating mode requirement, safer to nuclear power plant.
The control method is always in an isolated safe state after the regulating valve is closed until an operator accurately judges the working condition and then manually takes the next step of measures. Therefore, the invention is designed with a manual reset function, the isolation state can be reset manually after the regulating valve is closed, and the opening of the valve is regulated according to the water demand of the steam generator. That is, when the auxiliary feedwater regulating valve is triggered to automatically close, the auxiliary feedwater regulating valve is always in a closed state no matter how the liquid level of the steam generator changes. Therefore, radioactive media leaked from the primary loop in the SGTR accident steam generator are prevented from entering the secondary loop to cause radioactive leakage. At the moment, the residual heat of the core is led out through other non-isolated steam generators. If the auxiliary water supply function is isolated by mistake when the SGTR accident of the steam generator is not generated, an operator can adjust the control mode of the regulating valve to a specified opening degree from 0% after switching the control mode to a manual mode, and normal water supplement of the steam generator is ensured. The design is based on the design concept of deep defense, and provides a necessary manual backup means for the automatic functions of water replenishing and water isolating.
Examples
As shown in fig. 2, the present drawing only briefly outlines the control of the flow rate control valve of the auxiliary feed water electric pump, and the control strategy of the steam pump is the same.
When 001PO or 002PO is started, the auxiliary water supply system is put into operation, and at the moment, if a high signal of the liquid level of the steam generator appears, the electromagnetic valve in the row is triggered to be electrified. Taking column A as an example, when the starting state signal of 001PO or 002PO in column A and the steam generator water level high signal of column A are both present, the electromagnetic valve of column A is triggered to be electrified if no automatic opening instruction is given. Meanwhile, if the B-row electromagnetic valves are also triggered to be electrified, the two rows of electromagnetic valves are simultaneously electrified, and the change-over switch of 2 is triggered to switch, so that the regulating valve is forced to be opened to 0% of opening degree. The control pattern of 2 in the figure is: when the logic condition is 1, the switch outputs 'forced 0% opening'; when the operator needs manual adjustment, it is possible to switch to the manual mode setting regulating valve opening degree under any logic condition. The control pattern of 1 is: when the control instruction is 1, the electromagnetic valve is de-magnetized, 2-3 are conducted, and the valve is de-aerated and opened; when the control command is 0, the electromagnetic valve is excited, 1-2 is conducted, and the air inlet of the valve is adjusted.
If only one electromagnetic valve in the A row or the B row is electrified, the change-over switch cannot be triggered to forcibly output 0% opening degree, and the regulating valve is still in the full-open position. Therefore, the error closing of the regulating valve caused by the error triggering of the single-row signal can be avoided.
When the operator needs to adjust the opening of the regulating valve, two cases are considered: one is that the electromagnetic valves are all in a power-off state, the regulating valve is fully opened, the electromagnetic valves of the A column and the B column can be electrified by adopting manual reset signals of the A column and the B column respectively, at the moment, the selector switch is in a manual regulating state by default, and an operator regulates the opening of the valve through a manual regulating instruction; another situation is when the regulating valve has triggered automatic closing, where the operator can first reset the force isolation signal of the diverter switch and then make adjustments by manually adjusting the signal.
The implementation of the related logic relationship can be completed through logic configuration in the digital control system DCS, and can also be implemented by designing a special program module by using a programming principle.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations.
Claims (6)
1. A control method for preventing an auxiliary water supply system from causing overflow of a steam generator is characterized by comprising the following steps: the auxiliary water supply system is characterized in that an auxiliary water supply system of a water supply pipeline is formed after auxiliary water supply pumps of an A row and a B row are converged, regulating valves which are arranged on the water supply pipeline and provided with two electromagnetic valves respectively supplied with power by the A row and the B row are controlled, after any auxiliary water supply pump of the A row and the B row is started, the corresponding regulating valves are automatically opened in a linkage mode to replenish water, when the amount of the replenished water is too large and the A row and the B row simultaneously detect a high signal of a liquid level of a steam generator, the two electromagnetic valves respectively supplied with power by the A row and the B row are electrified through automatic interlocking, meanwhile, a regulating valve 0% opening instruction is given to close the regulating valves, the auxiliary water supply flow is cut off.
2. The control method for preventing the secondary water supply system from causing the overflow of the steam generator according to claim 1, wherein: the auxiliary water feeding pump comprises two electric pumps respectively belonging to the A row and the B row and two steam-driven pumps respectively belonging to the A row and the B row, and when any auxiliary water feeding pump of any row is started and simultaneously detects that the water level of the steam generator of the corresponding row reaches a high liquid level, the electromagnetic valve of the corresponding row is triggered to be electrified to enter a preparation isolation state.
3. The control method for preventing the secondary water supply system from causing the steam generator to overflow as set forth in claim 2, wherein: when the liquid level high signal of the steam generator is not detected in any column, the electromagnetic valve of the corresponding column is in a power-off state, and the corresponding regulating valve is in an opening state.
4. The control method for preventing the secondary water supply system from causing the overflow of the steam generator according to claim 1, wherein: the given regulating valve opening command of 0% is used for closing the regulating valve, namely two electromagnetic valves powered by the A row and the B row on a regulating valve air path are electrified at the same time, the opening command of 0% is triggered, and the air inflow is regulated to close the valve.
5. The control method for preventing the secondary water supply system from causing the steam generator to overflow as set forth in claim 4, wherein: after the auxiliary water supply regulating valve is triggered to be automatically closed, no matter how the liquid level of the steam generator changes, the auxiliary water supply regulating valve is always in a closed state until an operator accurately judges the working condition and then manually takes the next step of measures.
6. The control method for preventing the secondary water supply system from causing the steam generator to overflow as set forth in claim 5, wherein: if the auxiliary water supply function is isolated by mistake when the SGTR accident of the steam generator is not generated, an operator switches the control mode of the regulating valve into a manual mode, and then regulates the regulating valve to a specified opening degree from 0% opening degree, so that normal water supplement of the steam generator is ensured.
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Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103050161A (en) * | 2012-12-11 | 2013-04-17 | 中国核电工程有限公司 | Method for automatically isolating auxiliary water supply pipeline |
| CN203338776U (en) * | 2013-07-30 | 2013-12-11 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
| CN103474108A (en) * | 2013-09-03 | 2013-12-25 | 中国核电工程有限公司 | Safe replenishment method of auxiliary water supply system |
| CN204010702U (en) * | 2014-06-03 | 2014-12-10 | 中国核电工程有限公司 | A kind of steam generator emergency feedwater supply system |
| CN104681111A (en) * | 2015-01-08 | 2015-06-03 | 中国核电工程有限公司 | Auxiliary water supply flow segmented regulation control method |
| CN110726132A (en) * | 2019-09-05 | 2020-01-24 | 岭澳核电有限公司 | Method and system for supplying water to steam generator of nuclear power station under low-power working condition |
-
2020
- 2020-03-18 CN CN202010190136.9A patent/CN111486438B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103050161A (en) * | 2012-12-11 | 2013-04-17 | 中国核电工程有限公司 | Method for automatically isolating auxiliary water supply pipeline |
| CN203338776U (en) * | 2013-07-30 | 2013-12-11 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
| CN103474108A (en) * | 2013-09-03 | 2013-12-25 | 中国核电工程有限公司 | Safe replenishment method of auxiliary water supply system |
| CN204010702U (en) * | 2014-06-03 | 2014-12-10 | 中国核电工程有限公司 | A kind of steam generator emergency feedwater supply system |
| CN104681111A (en) * | 2015-01-08 | 2015-06-03 | 中国核电工程有限公司 | Auxiliary water supply flow segmented regulation control method |
| CN110726132A (en) * | 2019-09-05 | 2020-01-24 | 岭澳核电有限公司 | Method and system for supplying water to steam generator of nuclear power station under low-power working condition |
Non-Patent Citations (1)
| Title |
|---|
| 盛美玲等: ""华龙一号"应急给水系统热工水力分析", 《核科学与工程》 * |
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