CN103050157A - Water supply isolation device of optimized auxiliary water supply system - Google Patents
Water supply isolation device of optimized auxiliary water supply system Download PDFInfo
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- CN103050157A CN103050157A CN2012105321601A CN201210532160A CN103050157A CN 103050157 A CN103050157 A CN 103050157A CN 2012105321601 A CN2012105321601 A CN 2012105321601A CN 201210532160 A CN201210532160 A CN 201210532160A CN 103050157 A CN103050157 A CN 103050157A
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- valve
- feedwater
- steam generator
- gate valves
- water supply
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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
- Y02E30/30—Nuclear fission reactors
Abstract
The invention belongs to the technique of automatic control of nuclear power stations, and in particular relates to a water supply isolation device of an optimized auxiliary water supply system. An auxiliary water supply pipeline of each steam generator is provided with a plurality of electric gate valves which are supplied with power by A-series power supply systems and B-series power supply systems and are connected with a control system. According to the invention, auxiliary water supply of a damaged steam generator is isolated automatically under an SGTR (steam generator tube rupture) accident condition, so that the requirement that manual intervention is not allowed within certain time after the accident condition is met, and the hazard that an accident steam generator is subjected to spill-over under the accident condition is solved.
Description
Technical field
The invention belongs to the nuclear power station automatic control technology, be specifically related to a kind of device of optimizing auxiliary feedwater system feedwater isolation.
Background technology
Auxiliary feedwater system, can be guaranteed to steam generator supply chilled water when reactor has an accident and loses normal feedwater as one of engineered safeguards features, guarantees that in the decay heat of discharging reactor core the spill-over phenomenon does not occur steam generator.During particularly generating steam generator heat-transfer pipe breaks (SGTR) accident, need auxiliary feedwater system can isolate corresponding supply line, prevent the spill-over of SGTR accident steam generator.Auxiliary feedwater system to the pipeline synoptic diagram of steam generator feedwater as shown in Figure 1.
As shown in Figure 1, auxiliary feedwater system bio-occlusion Water flow-path is:
Electrodynamic pump water supply branch road is injected into feedwater in the steam generator 7 by isolation valve 5,6 inside and outside pneumatic control valve 1, hand stop valve 3, the containment;
The pneumatic pump branch road is injected into feedwater in the steam generator 7 by isolation valve 5,6 inside and outside pneumatic control valve 2, hand stop valve 4, the containment.
When the SGTR accident occurring and need to isolate auxiliary feedwater, can only arrive the hand stop valve 3,4 that the valve on-site manual closes on the corresponding steam generator water-supply line by the operator and realize isolation features, feedwater isolation synoptic diagram is as shown in Figure 2.
Development along with nuclear power technology, nuclear power station has proposed the requirement of three generations's nuclear power technology at present, need the power station to satisfy also automatically alleviation accident deterioration of accident conditions nonintervention in lower 30 minutes, and present solution can only be after accident just begins to carry out the accident mitigation operation in 30 minutes, therefore can't satisfy the requirement of three generations's nuclear power technology.
Needing the operator to arrive the scene of the accident after having an accident carries out the manual operation valve and also has certain risk.
Summary of the invention
The purpose of this invention is to provide the device of automatically feedwater of auxiliary feedwater system being isolated under a kind of SGTR of can be used for accident, improve the validity of auxiliary feedwater system and the security level of nuclear power station operation.
Technical scheme of the present invention is as follows: a kind of device of optimizing auxiliary feedwater system feedwater isolation, at every steam generator auxiliary feedwater pipeline some electric gate valves are set, some electric gate valves are powered respectively by A row electric power system and B row electric power system, and electric gate valve is connected with control system.
Further, the device of aforesaid optimization auxiliary feedwater system feedwater isolation, wherein, described some electric gate valves have four, the again parallel combination of connecting in twos, four electric gate valves all are in the normally open position, in two electric gate valves of series connection one by A row electric power system, another is powered by B row electric power system.
Further, the device of aforesaid optimization auxiliary feedwater system feedwater isolation, wherein, described some electric gate valves have four, the again parallel combination of connecting in twos, one is in normally open position, one and is in the Chang Guan position in two electric gate valves of series connection, and respectively by A row electric power system and the power supply of B row electric power system.
Further, the device of aforesaid optimization auxiliary feedwater system feedwater isolation, wherein, described some electric gate valves have four, distinguish parallel combination with two other again after two series connection, two electric gate valves of series connection are in the normally open position, and respectively by A row electric power system and the power supply of B row electric power system; Two electric gate valves in parallel are in the Chang Guan position separately, and respectively by A row electric power system and the power supply of B row electric power system.
Beneficial effect of the present invention is as follows: the present invention can realize under the accident conditions, automatism isolation to damaged steam generator auxiliary feedwater, satisfy the not requirement of needs manual intervention in the certain hour behind the accident conditions, solved the risk that may cause the spill-over of accident steam generator under the accident conditions.This device solves the potential risk of nuclear power station auxiliary feedwater function in the past, reduced the impact of human intervention factor on power plant safety, improved the validity of auxiliary feedwater system and the security level of nuclear power station operation.
Description of drawings
Fig. 1 is that auxiliary feedwater system is to the pipeline synoptic diagram of steam generator feedwater;
Fig. 2 is that auxiliary feedwater system is to the synoptic diagram of steam generator feedwater isolation;
Fig. 3 is embodiment 1 synoptic diagram of auxiliary feedwater system feedwater spacer assembly;
Fig. 4 is embodiment 2 synoptic diagram of auxiliary feedwater system feedwater spacer assembly;
Fig. 5 is embodiment 3 synoptic diagram of auxiliary feedwater system feedwater spacer assembly.
Embodiment
Below in conjunction with drawings and Examples the present invention is described in detail.
The present invention satisfies the designing requirement of ACP1000 heap type nuclear power station in order further to improve the security of auxiliary feedwater, sets up automatic isolating valve at steam generator auxiliary feedwater pipeline.When the SGTR accident, trigger the automatic isolating valve of this steam generator respective lines and close, isolate the auxiliary feedwater of the corresponding pipeline of steam generator that breaks, guarantee that spill-over does not occur the steam generator that breaks.
The outer isolation valve 5(non-return valve of containment on the present embodiment cancellation original steam generator auxiliary feedwater pipeline), newly-increased 4 electric gate valve 8-11, the again parallel combination of connecting in twos, as shown in Figure 3.
Increase by 4 electric gate valve 8-11 at the female pipe of steam generator moisturizing pipeline, wherein the power supply of valve 8(A row) and the power supply of valve 9(B row) series connection, valve 10(B is listed as power supply) and the power supply of valve 11(A row) series connection, and then be arranged in parallel.Between the auxiliary feedwater system standby period, valve 9 and valve 11 are in Chang Guan position (getting the outer isolation valve function of containment), and valve 8 and valve 10 are in the normally open position, newly establish 4 electric gate valves and can both satisfy the requirement that fault keeps original position.
When auxiliary feedwater system started, by startup command Open valve 9 and valve 11, then electrodynamic pump carried out moisturizing operation through relevant pipeline and valve to steam generator with pneumatic pump.When the SGTR accident occurs, trigger the automatism isolation signal of electric gate valve 8-11, the feedwater of automatism isolation steam generator by the low liquid level setting valve of high liquid level setting valve stack voltage stabilizer of Steam Generators in NPP.Can realize the function of self water feeding and automatism isolation satisfying the requirement of three generations's nuclear power technology by this scheme.
Present embodiment keeps the outer isolation valve 5 of containment, newly-increased 4 electric gate valve 8-11, and the again parallel combination of connecting in twos, as shown in Figure 4.
Increase by 4 electric gate valve 8-11 at the female pipe of steam generator moisturizing pipeline, wherein the power supply of valve 8(A row) and the power supply of valve 9(B row) series connection, valve 10(B is listed as power supply) and the power supply of valve 11(A row) series connection, and then be arranged in parallel.Between the auxiliary feedwater system standby period, newly establish 4 electric gate valves and all be in the normally open position, can satisfy the requirement that fault keeps original position simultaneously.
When auxiliary feedwater system started, by the enforced opening order of enabling signal triggering valve 8-11, electrodynamic pump carried out moisturizing operation through relevant pipeline and valve to steam generator with pneumatic pump.When the SGTR accident occurs, trigger the automatism isolation signal of electric gate valve 8-11, the feedwater of automatism isolation steam generator by the low liquid level setting valve of high liquid level setting valve stack voltage stabilizer of Steam Generators in NPP.Can realize the function of self water feeding and automatism isolation satisfying the requirement of three generations's nuclear power technology by this scheme.
Present embodiment increases 4 electric gate valve 8-11 newly, wherein distinguishes parallel combination with two other again after two series connection, as shown in Figure 5.
Increase by 4 electric gate valve 8-11 at the female pipe of steam generator moisturizing pipeline, wherein the power supply of valve 8(A row) and the power supply of valve 9(B row) series connection, power with valve 10(B row afterwards), valve 11(A is listed as power supply) in parallel.Between the auxiliary feedwater system standby period, valve 8 and valve 9 are in the normally open position, and valve 10 and valve 11 are in the Chang Guan position, and newly-increased 4 motorized valves can both satisfy the requirement that failsafe valve keeps original position simultaneously.
When auxiliary feedwater system started, by the enforced opening order of enabling signal triggering valve 8 and valve 9, electrodynamic pump carried out moisturizing operation through relevant pipeline and valve to steam generator with pneumatic pump.When the SGTR accident occurs, trigger the automatism isolation signal of electric gate valve 8-11, the feedwater of automatism isolation steam generator by the low liquid level setting valve of high liquid level setting valve stack voltage stabilizer of Steam Generators in NPP.Can realize the function of self water feeding and automatism isolation satisfying the requirement of three generations's nuclear power technology by this scheme.
Obviously, those skilled in the art can carry out various changes and modification to the present invention and not break away from the spirit and scope of the present invention.Like this, if of the present invention these are revised and modification belongs within the scope of claim of the present invention and equivalent technology thereof, then the present invention also is intended to comprise these changes and modification interior.
Claims (4)
1. optimize the device that the auxiliary feedwater system feedwater is isolated for one kind, it is characterized in that: the auxiliary feedwater pipeline at every steam generator arranges some electric gate valves, some electric gate valves are powered respectively by A row electric power system and B row electric power system, and electric gate valve is connected with control system.
2. the device of optimization auxiliary feedwater system as claimed in claim 1 feedwater isolation, it is characterized in that: described some electric gate valves have four, the again parallel combination of connecting in twos, four electric gate valves all are in the normally open position, the series connection two electric gate valves in one by A row electric power system, another is powered by B row electric power system.
3. the device of optimization auxiliary feedwater system as claimed in claim 1 feedwater isolation, it is characterized in that: described some electric gate valves have four, the again parallel combination of connecting in twos, one is in normally open position, one and is in the Chang Guan position in two electric gate valves of series connection, and respectively by A row electric power system and the power supply of B row electric power system.
4. the device of optimization auxiliary feedwater system as claimed in claim 1 feedwater isolation, it is characterized in that: described some electric gate valves have four, distinguish parallel combination with two other again after two series connection, two electric gate valves of series connection are in the normally open position, and respectively by A row electric power system and the power supply of B row electric power system; Two electric gate valves in parallel are in the Chang Guan position separately, and respectively by A row electric power system and the power supply of B row electric power system.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201210532160.1A CN103050157B (en) | 2012-12-11 | 2012-12-11 | A kind of auxiliary feedwater system of optimizing is to the device of water segregation |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201210532160.1A CN103050157B (en) | 2012-12-11 | 2012-12-11 | A kind of auxiliary feedwater system of optimizing is to the device of water segregation |
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| CN103050157A true CN103050157A (en) | 2013-04-17 |
| CN103050157B CN103050157B (en) | 2015-07-29 |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN103474117A (en) * | 2013-09-03 | 2013-12-25 | 中国核电工程有限公司 | Safety supply method of auxiliary water supply system through adding of by-pass pipelines |
| WO2015014046A1 (en) * | 2013-07-30 | 2015-02-05 | 中广核工程有限公司 | Nuclear power station vapor generator auxiliary feedwater system |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
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| US4113561A (en) * | 1976-05-17 | 1978-09-12 | Westinghouse Electric Corp. | Valve arrangement for a nuclear plant residual heat removal system |
| US4231328A (en) * | 1978-07-18 | 1980-11-04 | Westinghouse Electric Corp. | Automatic steam generator feedwater realignment system |
| CN1550019A (en) * | 2001-07-24 | 2004-11-24 | ����ͨAnp����˾ | Method and device for supplying pressurised water to a steamgenerator of a nuclear reactor during shut-down periods of the reactor |
| CN102693765A (en) * | 2011-03-23 | 2012-09-26 | 巴布科克和威尔科克斯核能股份有限公司 | Emergency core cooling system for pressurized water reactor |
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2012
- 2012-12-11 CN CN201210532160.1A patent/CN103050157B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4113561A (en) * | 1976-05-17 | 1978-09-12 | Westinghouse Electric Corp. | Valve arrangement for a nuclear plant residual heat removal system |
| US4231328A (en) * | 1978-07-18 | 1980-11-04 | Westinghouse Electric Corp. | Automatic steam generator feedwater realignment system |
| CN1550019A (en) * | 2001-07-24 | 2004-11-24 | ����ͨAnp����˾ | Method and device for supplying pressurised water to a steamgenerator of a nuclear reactor during shut-down periods of the reactor |
| CN102693765A (en) * | 2011-03-23 | 2012-09-26 | 巴布科克和威尔科克斯核能股份有限公司 | Emergency core cooling system for pressurized water reactor |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2015014046A1 (en) * | 2013-07-30 | 2015-02-05 | 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 |
| CN103474117A (en) * | 2013-09-03 | 2013-12-25 | 中国核电工程有限公司 | Safety supply method of auxiliary water supply system through adding of by-pass pipelines |
| CN103474117B (en) * | 2013-09-03 | 2016-08-17 | 中国核电工程有限公司 | A kind of safe replenishing method of auxiliary feedwater system increasing bypass line |
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| CN103050157B (en) | 2015-07-29 |
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