CN103778984A - Water supply system adopting once-through steam generator reactor - Google Patents
Water supply system adopting once-through steam generator reactor Download PDFInfo
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- CN103778984A CN103778984A CN201210405915.1A CN201210405915A CN103778984A CN 103778984 A CN103778984 A CN 103778984A CN 201210405915 A CN201210405915 A CN 201210405915A CN 103778984 A CN103778984 A CN 103778984A
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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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Abstract
The invention belongs to the field of a nuclear reactor and particularly relates to a water supply system adopting a once-through steam generator reactor. The water supply system comprises a water supply pipe group, a water supply adjusting station with one end connected with the water supply pipe group and a water feeding pipe group with one end connected with the other end of the water supply adjusting station. The other end of the water supply pipe group is connected with a water supply pipeline of a once-through steam generator, and a main water supply pump is arranged on the water supply pipe group. Flow quantity and pressure of water supply can be controlled together by adjusting rotation speed and inlet steam quantity of a water supply pump of a pneumatic water supply pump and by adjusting opening degree of a main water supply adjusting valve. The water supply adjusting station directly controls total flow quantity of water supplied to the once-through steam generator, system configuration and control are simplified, and a water supply isolating valve can isolate water fast under an accidental working condition.
Description
Technical field
The invention belongs to nuclear reactor field, be specifically related to a kind of a kind of water supply system that adopts once through steam generator reactor that is applicable to.
Background technology
The steam generator that nuclear power station adopts both at home and abroad mostly at present is natural circulation steam generator, and in natural circulation steam generator, secondary side moves with natural circulation mode, and feedwater is heated to form steam within the ascent stage; Steam generator secondary side has certain hydrosolvent, only needs to control well steam generator water level, just can regulate according to the needs of secondary circuit the output of heap power and steam.And secondary side is to adopt forced circulation to flow through its heat exchanging part to produce steam in once through steam generator, feedwater flow and pressure directly affect steam quality and output.Therefore, the characteristic of once through steam generator is had higher requirement to the performance of water supply system.
But, once through steam generator has little, lightweight, the efficient advantage of volume, many small-sized DC steam generators are placed in reactor pressure vessel, and it is integrated that realization response is piled, and is conducive to improve security, reliability, compact and the advance of reactor assembly.Therefore, Novel small-sized heap has adopted once through steam generator mostly at present.In order to meet the requirement of the pressure of once through steam generator to feedwater flow and pressure, configure corresponding water supply system.
Summary of the invention
The object of this invention is to provide a kind of water supply system that can meet the requirement of the reactor that has adopted once through steam generator to feedwater flow and pressure,
In order to realize object of the present invention, by the following technical solutions, a kind of water supply system that adopts once through steam generator reactor, comprise, the feed pipe group that the feedwater that feed pipe group, one end are connected with described feed pipe group regulates station, one end to regulate the station other end to be connected with feedwater, the other end of described feed pipe group is connected with once through steam generator supply line, in described feed pipe group, is provided with main feed pump.
Further described feedwater regulates station to comprise main feedwater adjustable pipe and bypass feedwater adjustable pipe, and one end away from feedwater adjusting station of described main feedwater adjustable pipe and bypass feedwater adjustable pipe is connected to described feed pipe group; On main feedwater adjustable pipe and bypass feedwater adjustable pipe, be provided with variable valve.
Further described feed pipe group comprises two pipelines in parallel, and one end away from feedwater adjusting station of these two parallel pipelines is connected with the sender property outlet of feed-water deaerator system.
Further feed pipe group comprises two pipelines in parallel, these two parallel pipelines regulate the one end at station to be connected with the supply line of once through steam generator away from feedwater.
Further described main feed pump is multistage centrifugal steam-operating speed-variable pump.
The present invention has following technique effect:
(1) normal power run duration, for guaranteeing that once through steam generator secondary side outlet steam is certain value, by pressure and the flow of multistage centrifugal steam-operating speed-variable pump and the feedwater of main feed-regulating valve co-controlling, makes it to meet the demands.Because once through steam generator does not have water level, therefore, can only, using vapor (steam) temperature, vapor pressure, feedwater flow, feed pressure etc. as control signal, can realize by the adjusting rotating speed of steam feed pump and the aperture of throttle flow and main feed-regulating valve flow and the pressure of co-controlling feedwater to water management;
(2) feedwater regulates to stand erectly to connect and controls the total flow supplying water to once through steam generator, and system configuration is simplified, and controls and simplifies;
(3) feedwater isolation valve can be by feedwater isolation fast under accident conditions.
Accompanying drawing explanation
Fig. 1 is integral reactor water supply system schematic diagram of the present invention
Wherein: 1 is main feed pump; 2 is main feed pump outlet non-return valve; 3 is main feed pump outlet isolation valve; 4 is the first main feed water isolating valve; 5 is main feed-regulating valve; 6 is the second main feed water isolating valve; 7 is the firstth bypass feedwater isolation valve; 8 is bypass feed-regulating valve; 9 is the second bypass feedwater isolation valve; 10 is flowmeter; 11 is orifice plate; 12 is feed water check valve; 13 is containment; 14 is once through steam generator; 15 is feed pipe group; 16 stand for feedwater regulates; 17 is feed pipe group; 18 is feedwater deaerating system.
Embodiment
Below in conjunction with Fig. 1 and embodiment, the present invention is further illustrated.
A water supply system that adopts once through steam generator reactor, comprising: the feed pipe group 15, the feedwater that are connected in series successively regulate station 16 and feed pipe group 17;
Described feed pipe group 15 comprises two supply lines in parallel, one end away from feedwater adjusting station 16 of these two supply lines in parallel is connected with the sender property outlet of feed-water deaerator system 18, and the other end of these two supply lines in parallel is connected to described feedwater and regulates station 16; Article two, supply line in parallel is from regulating station 16 ends to be all furnished with successively main feed pump 1, main feed pump outlet non-return valve 2 and main feed pump outlet isolation valve 3 near feed-water deaerator system 18 ends to close feedwater.Described main feed pump 1 is multistage centrifugal steam-operating speed-variable pump.Described multistage centrifugal steam-operating speed-variable pump drives by fired multi-stage condensation type variable-speed turbine, and the admission of this fired multi-stage condensation type variable-speed turbine is provided by drawing gas of power station main steam turbine, and exhaust steam enters power station main condenser.
Described feedwater adjusting station 16 comprises main feedwater adjustable pipe and bypass feedwater adjustable pipe, and one end away from feedwater adjusting station of described main feedwater adjustable pipe and bypass feedwater adjustable pipe is connected to described feed pipe group 15; On described main feedwater adjustable pipe, be disposed with the first main feed water isolating valve 4, main feed-regulating valve 5 and the second main feed water isolating valve 6 from close feed pipe group end to close feed pipe group end; On described bypass feedwater adjustable pipe, be disposed with the first bypass feedwater isolation valve 7, bypass feed-regulating valve 8 and the second bypass feedwater isolation valve 9 from close feed pipe group end to close feed pipe group end;
Feedwater, after main feed pump 1 boosts, is delivered to feedwater and regulates station 16, and when normal power operation, feedwater flow is regulated by main feed-regulating valve 5, and now bypass valve 8 is closed.Feedwater regulates station to enter feed pipe group 17 after 16 adjust fluxes through feedwater, and is divided into 2 1/2 water supply arms, every 1/2 water supply arm penetrate containment 13 interior after, be respectively once through steam generator 14 and supply water.
Claims (5)
1. one kind adopts the water supply system of once through steam generator reactor, its spy is being: comprise, the feed pipe group that the feedwater that feed pipe group, one end are connected with described feed pipe group regulates station, one end to regulate the station other end to be connected with feedwater, the other end of described feed pipe group is connected with once through steam generator supply line, in described feed pipe group, is provided with main feed pump.
2. water supply system as claimed in claim 1, its spy is being: described feedwater regulates station to comprise main feedwater adjustable pipe and bypass feedwater adjustable pipe, and one end away from feedwater adjusting station of described main feedwater adjustable pipe and bypass feedwater adjustable pipe is connected to described feed pipe group; On main feedwater adjustable pipe and bypass feedwater adjustable pipe, be provided with variable valve.
3. water supply system as claimed in claim 1, its spy is being: described feed pipe group comprises two pipelines in parallel, one end away from feedwater adjusting station of these two parallel pipelines is connected with the sender property outlet of feed-water deaerator system.
4. water supply system as claimed in claim 1, its spy is being: feed pipe group comprises two pipelines in parallel, these two parallel pipelines away from feedwater regulate station one end be connected with the supply line of once through steam generator.
5. water supply system as claimed in claim 1, its spy is being: described main feed pump is multistage centrifugal steam-operating speed-variable pump.
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CN201210405915.1A CN103778984A (en) | 2012-10-23 | 2012-10-23 | Water supply system adopting once-through steam generator reactor |
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CN201210405915.1A CN103778984A (en) | 2012-10-23 | 2012-10-23 | Water supply system adopting once-through steam generator reactor |
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Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106297925A (en) * | 2016-07-28 | 2017-01-04 | 董哲 | The water-supply scheme of a kind of multi-module type HTGR Nuclear Power Plant, dynamic model and regulation and control method |
CN107145175A (en) * | 2017-05-26 | 2017-09-08 | 中国核动力研究设计院 | A kind of steam generator feed temperature controls simulation system |
CN109686462A (en) * | 2018-12-04 | 2019-04-26 | 中广核研究院有限公司 | Reactor RHR system and method based on once through steam generator |
CN112420231A (en) * | 2020-11-20 | 2021-02-26 | 西安热工研究院有限公司 | Method for controlling outlet temperature of direct-flow steam generator of nuclear power station |
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CN1252607A (en) * | 1998-10-22 | 2000-05-10 | Abb燃烧工程核力公司 | Water supply control in full power range for pressurized water reactor steam generator |
JP2003176901A (en) * | 2001-12-10 | 2003-06-27 | Kurita Water Ind Ltd | Method for controlling boiler system |
JP3544689B2 (en) * | 1993-08-06 | 2004-07-21 | バブコック日立株式会社 | Start-up controller for variable-pressure once-through boiler |
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 |
CN202948744U (en) * | 2012-10-22 | 2013-05-22 | 中国核动力研究设计院 | Water supply system adopting once-through steam generator reactor |
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2012
- 2012-10-23 CN CN201210405915.1A patent/CN103778984A/en active Pending
Patent Citations (5)
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JP3544689B2 (en) * | 1993-08-06 | 2004-07-21 | バブコック日立株式会社 | Start-up controller for variable-pressure once-through boiler |
CN1252607A (en) * | 1998-10-22 | 2000-05-10 | Abb燃烧工程核力公司 | Water supply control in full power range for pressurized water reactor steam generator |
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 |
JP2003176901A (en) * | 2001-12-10 | 2003-06-27 | Kurita Water Ind Ltd | Method for controlling boiler system |
CN202948744U (en) * | 2012-10-22 | 2013-05-22 | 中国核动力研究设计院 | Water supply system adopting once-through steam generator reactor |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106297925A (en) * | 2016-07-28 | 2017-01-04 | 董哲 | The water-supply scheme of a kind of multi-module type HTGR Nuclear Power Plant, dynamic model and regulation and control method |
CN107145175A (en) * | 2017-05-26 | 2017-09-08 | 中国核动力研究设计院 | A kind of steam generator feed temperature controls simulation system |
CN109686462A (en) * | 2018-12-04 | 2019-04-26 | 中广核研究院有限公司 | Reactor RHR system and method based on once through steam generator |
CN112420231A (en) * | 2020-11-20 | 2021-02-26 | 西安热工研究院有限公司 | Method for controlling outlet temperature of direct-flow steam generator of nuclear power station |
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Application publication date: 20140507 |