CN101625905A - Auxiliary water feed system of nuclear power plant - Google Patents
Auxiliary water feed system of nuclear power plant Download PDFInfo
- Publication number
- CN101625905A CN101625905A CN200910108974A CN200910108974A CN101625905A CN 101625905 A CN101625905 A CN 101625905A CN 200910108974 A CN200910108974 A CN 200910108974A CN 200910108974 A CN200910108974 A CN 200910108974A CN 101625905 A CN101625905 A CN 101625905A
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- China
- Prior art keywords
- water feed
- nuclear power
- power plant
- auxiliary water
- feed
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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 provides an auxiliary water feed system of a nuclear power plant, comprising a water feed box and a water feed pump connected with the water feed box. A small flow reflux device is connected between an outlet pipeline of the water feed pump and the water feed box, and the reflux device is respectively communicated with the outlet pipeline of the water feed pump and the water feed box. When the small flow reflux device is arranged between the outlet pipeline of the water feed pump and the water feed box, the water feed pump leads a part of fluid to the water feed box through the reflux device under the working condition of small flow so as to change the flow of the water feed pump, thereby effectively preventing shock excitation of the fluid.
Description
Technical field
The invention belongs to the nuclear power generating equipment field, relate in particular to a kind of auxiliary water feed system of nuclear power plant.
Background technology
Feed pump its source line vibration under low flow rate condition that the machine stage of rising of the L103 overhaul of mountain range Australia nuclear power station is found auxiliary water feed system of nuclear power plant is high, and the vibration of the feed-tank of its upstream is also very big, and feed pump pump intake pipeline vibration under the full flow operating mode is very little.By analysis, feed pump causes the fluid exciting easily under the low discharge operating condition of test.
Prior art discloses a kind of high power water boiler solution nuclear reactor heap air circuit and circulating line wherein, circulating line is connected with water pump with cyclic water tank, make circulating line that certain natural-circulation capacity be arranged, but the unresolved problem that how to reduce the fluid exciting.
Summary of the invention
The technical problem to be solved in the present invention is, a kind of auxiliary water feed system of nuclear power plant is provided, and can reduce fluid exciting problem under low flow rate condition.
In order to solve the problems of the technologies described above, the invention provides a kind of auxiliary water feed system of nuclear power plant, comprise feed-tank and the feed pump that is connected with described feed-tank.Be connected with the low discharge reflux between the discharge pipe of described feed pump and described feed-tank, described reflux communicates with the discharge pipe and the described feed-tank of described feed pump respectively.
More specifically, described reflux comprises miniflow line, control valve and throttling orifice plate, described control valve and throttling orifice plate all are arranged on the described miniflow line, and connect by described miniflow line, described control valve is connected with described feed pump by described miniflow line, and described throttling orifice plate is connected with described feed-tank by miniflow line.
More specifically, described miniflow line is provided with the switching control pilot door, and described switching control pilot door opens when low flow rate condition, close during big flow operating mode.
More specifically, described switching control pilot Men Yuyi logic control device connects.
More specifically, the design discharge of described reflux is greater than the source line vibration obvious return flow improved of described reflux at described feed pump.
More specifically, described design discharge is greater than 8m
3/ h.
More specifically, described throttling orifice plate is of a size of according to described design discharge and calculates and the size of gained.
More specifically, described throttling orifice plate aperture is 6.5mm.
More specifically, described feed pump is a pneumatic pump.
After between the discharge pipe of feed pump and the feed-tank low discharge reflux being set, feed pump draws back feed-tank with segment fluid flow by reflux under low flow rate condition, change the flow of feed pump, thereby has effectively prevented the exciting of fluid.
Description of drawings
Fig. 1 is the structural representation of a kind of auxiliary water feed system of nuclear power plant of providing of the embodiment of the invention.
Embodiment
In order to make the technical problem to be solved in the present invention, technical scheme and beneficial effect clearer,, the present invention is further elaborated below in conjunction with drawings and Examples.Should be appreciated that specific embodiment described herein only in order to explanation the present invention, and be not used in qualification the present invention.
See also Fig. 1, the embodiment of the invention provides a kind of auxiliary water feed system of nuclear power plant, comprises feed-tank 1 and the feed pump 2 that is connected with feed-tank 1.Be connected with low discharge reflux 3 between the discharge pipe 21 of feed pump 2 and feed-tank 1, this reflux 3 communicates with the discharge pipe 21 and the feed-tank 1 of feed pump 2 respectively.
Particularly, feed pump 2 is arranged at the downstream of feed-tank 1, and the source line 22 of feed pump 2 is connected with the outlet of feed-tank 1, to pump the water in the feed-tank 1.Feed pump 2 can be pneumatic pump, to make things convenient for electrical control, reaches the efficient that improves pump water.
Above-mentioned reflux 3 comprises miniflow line 31, control valve 32 and throttling orifice plate 33.Control valve 32 and throttling orifice plate 33 all are arranged on the miniflow line 31, connect by this miniflow line 31 between them.Control valve 32 is connected with the discharge pipe of feed pump 2 by miniflow line 31, and throttling orifice plate 33 is connected with feed-tank 1 by miniflow line 31.The water that refluxes from feed pump 2 can pass through control valve 32 and throttling orifice plate 33, enters feed-tank 1, and control valve 32 and throttling orifice plate 33 guarantee that according to the traffic requirement setting under the low flow rate condition, the flow of backflow can the eliminate fluid exciting.
After connecting reflux 3, the effective discharge of feed pump 2 discharge pipes 21 can reduce, if this flow can not satisfy request for utilization, can between control valve 32 and feed pump 2, be provided with switching control pilot door 34, switching control pilot door 34 opens when low flow rate condition, close during big flow operating mode.Switching control pilot door 34 can also be connected with a logic control device (not shown), to move by this logic control device automatic control switch according to the flow size.
Like this, in order to increase the flow of feed pump 2 under low flow rate condition, therefore designed backflow miniflow line 31.Among the embodiment, feed pump 2 adopts ULZER HPcp 150-210-5s, and under low flow rate condition, the rate of discharge of feed pump 2 is 8.7m
3/ h, under big flow operating mode, the rate of discharge of feed pump 2 is 202m
3/ h.By increasing the method for miniflow line 31, make auxiliary feedwater pneumatic pump source line vibration maximal value be reduced to 35mm/s by 127mm/s, solved the problem of pump intake pipeline vibration effectively.
In addition, the design discharge of miniflow line 21 can be determined according to test findings in the reflux 3, when feed pump 2 operations, regulate the flow of pump, the flow that refluxes when finding its source line 21 vibrations to have clear improvement, and the design discharge of backflow miniflow line 31 should be greater than this flow.Through the test determination return flow at 8m
3During/h, source line 21 vibrations of feed pump 2 can have clear improvement.
Throttling orifice plate 32 is of a size of according to above-mentioned design discharge and calculates and the size of gained, to obtain the optimum dimension of throttling orifice plate 32.In the present embodiment, throttling orifice plate 32 is three grades of throttling orifice plates, and the aperture of each grade (diameter) is 6.5mm.
Therefore, after between the discharge pipe 21 of feed pump 2 and the feed-tank 1 low discharge reflux 3 being set, feed pump 2 draws back feed-tank 1 with segment fluid flow by reflux 3 under low flow rate condition, change the flow of feed pump 2, thereby effectively prevented the exciting of fluid.
The above only is preferred embodiment of the present invention, not in order to restriction the present invention, all any modifications of being done within the spirit and principles in the present invention, is equal to and replaces and improvement etc., all should be included within protection scope of the present invention.
Claims (9)
1, a kind of auxiliary water feed system of nuclear power plant, comprise feed-tank and the feed pump that is connected with described feed-tank, it is characterized in that: be connected with the low discharge reflux between the discharge pipe of described feed pump and described feed-tank, described reflux communicates with the discharge pipe and the described feed-tank of described feed pump respectively.
2, auxiliary water feed system of nuclear power plant as claimed in claim 1, it is characterized in that: described reflux comprises miniflow line, control valve and throttling orifice plate, described control valve and throttling orifice plate all are arranged on the described miniflow line, and connect by described miniflow line, described control valve is connected with described feed pump by described miniflow line, and described throttling orifice plate is connected with described feed-tank by miniflow line.
3, auxiliary water feed system of nuclear power plant as claimed in claim 2 is characterized in that: described miniflow line is provided with the switching control pilot door, and described switching control pilot door opens when low flow rate condition, close during big flow operating mode.
4, auxiliary water feed system of nuclear power plant as claimed in claim 3 is characterized in that: described switching control pilot Men Yuyi logic control device connects.
5, auxiliary water feed system of nuclear power plant as claimed in claim 2 is characterized in that: the design discharge of described reflux is greater than the source line vibration obvious return flow improved of described reflux at described feed pump.
6, auxiliary water feed system of nuclear power plant as claimed in claim 5 is characterized in that: described design discharge is greater than 8m
3/ h.
7, auxiliary water feed system of nuclear power plant as claimed in claim 5 is characterized in that: described throttling orifice plate is of a size of according to described design discharge and calculates and the size of gained.
8, auxiliary water feed system of nuclear power plant as claimed in claim 7 is characterized in that: described throttling orifice plate aperture is 6.5mm.
9, as each described auxiliary water feed system of nuclear power plant of claim 1-8, it is characterized in that: described feed pump is a pneumatic pump.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200910108974A CN101625905A (en) | 2009-07-22 | 2009-07-22 | Auxiliary water feed system of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200910108974A CN101625905A (en) | 2009-07-22 | 2009-07-22 | Auxiliary water feed system of nuclear power plant |
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| CN101625905A true CN101625905A (en) | 2010-01-13 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN200910108974A Pending CN101625905A (en) | 2009-07-22 | 2009-07-22 | Auxiliary water feed system of nuclear power plant |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101936289A (en) * | 2010-09-19 | 2011-01-05 | 中国广东核电集团有限公司 | Device and method for emergency stop protection and periodic test of steam main feed pump |
| CN102750994A (en) * | 2012-06-25 | 2012-10-24 | 中国核电工程有限公司 | Method for reducing temperature of seal injected water for nuclear power station main pump |
| CN103460299A (en) * | 2011-03-30 | 2013-12-18 | 西屋电气有限责任公司 | Self-contained emergency spent nuclear fuel pool cooling 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 |
| CN103871508A (en) * | 2012-12-13 | 2014-06-18 | 中国核动力研究设计院 | Auxiliary water supply tank stored water circulation cooling system |
| CN104806552A (en) * | 2014-01-24 | 2015-07-29 | 上海华林工业气体有限公司 | Condensate pump circuit long in service life and capable of preventing pipeline erosion |
| CN105327954A (en) * | 2015-11-15 | 2016-02-17 | 金杯电工衡阳电缆有限公司 | Cable finely-drawing device |
| CN105788686A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Water-supply medicine adding system for nuclear power plant |
-
2009
- 2009-07-22 CN CN200910108974A patent/CN101625905A/en active Pending
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101936289A (en) * | 2010-09-19 | 2011-01-05 | 中国广东核电集团有限公司 | Device and method for emergency stop protection and periodic test of steam main feed pump |
| CN101936289B (en) * | 2010-09-19 | 2013-01-23 | 中国广东核电集团有限公司 | Device and method for emergency stop protection and periodic test of steam main feed pump |
| CN103460299A (en) * | 2011-03-30 | 2013-12-18 | 西屋电气有限责任公司 | Self-contained emergency spent nuclear fuel pool cooling system |
| CN103460299B (en) * | 2011-03-30 | 2016-03-16 | 西屋电气有限责任公司 | Self-contained emergent spent nuclear fuel pool cooling system |
| CN102750994A (en) * | 2012-06-25 | 2012-10-24 | 中国核电工程有限公司 | Method for reducing temperature of seal injected water for nuclear power station main pump |
| CN103871508A (en) * | 2012-12-13 | 2014-06-18 | 中国核动力研究设计院 | Auxiliary water supply tank stored water circulation cooling 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 |
| CN104806552A (en) * | 2014-01-24 | 2015-07-29 | 上海华林工业气体有限公司 | Condensate pump circuit long in service life and capable of preventing pipeline erosion |
| CN105327954A (en) * | 2015-11-15 | 2016-02-17 | 金杯电工衡阳电缆有限公司 | Cable finely-drawing device |
| CN105788686A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Water-supply medicine adding system for nuclear power plant |
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Application publication date: 20100113 |