CN201648058U - Fine filter system for steam generator of nuclear power station - Google Patents
Fine filter system for steam generator of nuclear power station Download PDFInfo
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- CN201648058U CN201648058U CN2009200583851U CN200920058385U CN201648058U CN 201648058 U CN201648058 U CN 201648058U CN 2009200583851 U CN2009200583851 U CN 2009200583851U CN 200920058385 U CN200920058385 U CN 200920058385U CN 201648058 U CN201648058 U CN 201648058U
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Abstract
The utility model relates to a fine filter system for a steam generator of a nuclear power station, which is characterized by comprising a prefilter (1) and a back filter (2), wherein the prefilter (1) is formed by cation exchange resin (1-1) and mixed ion exchange resin (1-2) or by the mixed ion exchange resin (1-2); and the back filter (2) is formed by connecting a resin catcher (2-1) and an ultrafilter (2-2) in series. The utility model can catch broken resin with large grains, broken resin with small grains and graininess impurities with the granularity being smaller than 0.2 mm, which are leaked after condensed water is treated by the prefilter (1), therefore, the broken resin is prevented from entering a secondary loop and generating sulfate ions in the presence of high temperature to result in the concentration of the sulfate ions in the gap position of the steam generator, the formation of an acid corrosive environment and the induction of the phenomena of corrosion fracture and the like of a heat transfer tube of the steam generator.
Description
Technical field
The utility model is used for the smart filtration filtering system of nuclear power station steam generator, is applicable to the control of Nuclear power plants secondary circuit vapour generator water and steam quality.Belong to Nuclear power plants auxiliary facility technical field.
Background technology
The life-span of nuclear power station steam generator influences the life-span of Nuclear power plants to a great extent, and the feed water quality of Nuclear power plants secondary circuit vapour generator has direct influence to life-span of nuclear power station steam generator.Because the water of supplying with vapour generator finishes the condensed water of steam cooling after the merit by steam turbine and the supplementary feed of desalting system is formed, wherein condensed water accounts for vapour generator and gives more than 90% of water inventory, so the quality of condensed water directly has influence on the quality of vapour generator feedwater.If condensed water is not carried out respective handling, bring very big influence can for the work of Nuclear power plants unit, mainly comprise: (1) is installed at unit and is finished, during the initial start-up, require a great deal of time and carry out system's flushing, every unit is whenever sent out an atmospheric electricity less, and Nuclear power plants will lack 1,000,000 dollars income; (2) because the leakage of condenser, brought very big threat for the safety and economic operation of unit, if set up condensed water filtration treatment device, can keep unit during little leakages of condenser and normally move, system's flush time in the time of can guaranteeing when leaking greatly that unit safety shutdown and saving are restarted.Therefore, how to control the water and steam quality of Nuclear power plants secondary circuit, remove metallic corrosion products, suspended substance and the salt impurity in the condensed water and prevent that the broken ion exchange resin condensate system technology of bleeding from being the problem of paying close attention to the most in the industry.
In the prior art, generally be to adopt Zeo-karb or mixture iron exchange resin strainer that condensed water is carried out filtration treatment.But have following aspect defective: the ion exchange resin of (1) band sulfonic acid group is brought secondary circuit into by condensed water stripping sulfate ion; (2) ion-exchanger produces the less fragmentation of a small amount of granularity because of high velocity flow or frequent conveying, pressurized air scouring etc., can pass the water cap of ion-exchanger bottom and the resin catcher of mixture iron exchange resin device outlet, go into secondary circuit with condensed water, pyrolytic decomposition produces sulfate ion.Therefore, the described ion exchange system of prior art causes the nuclear power station steam generator sulfate radical to exceed standard easily.And the sulfate radical plasma concentration exceeds standard, and not only can influence the chemical property index of Nuclear power plants, also concentrates in the position, slit of the vapour generator development of heat easily, forms oxidisability, acid attack environment, brings out the corrosion failure of steam generator heat-transfer pipe.
The utility model content
The purpose of this utility model is in order to solve the problem that the above-mentioned Nuclear power plants secondary circuit vapour generator sulfate radical that causes owing to the small-particle resin exceeds standard, to be provided for the smart filtration filtering system of nuclear power station steam generator.
The purpose of this utility model can realize by the following technical solutions:
Be used for the smart filtration filtering system of nuclear power station steam generator, it is characterized in that: comprise fore filter and post-filter; The inlet end of fore filter is connected with the condensed water delivery port of the main condensate pump of nuclear power station steam generator, the exit end of fore filter is divided into two tunnel preposition output loops, and one of preposition output loop is connected with the inlet end of fore filter, two being connected with the inlet end of post-filter of preposition output loop; The exit end of post-filter is divided into two tunnel rearmounted output loops, and one of rearmounted output loop is connected with the inlet end of fore filter, and two of rearmounted output loop is connected with the inlet end of Nuclear power plants secondary circuit vapour generator.
The purpose of this utility model can also be achieved through the following technical solutions:
A kind of embodiment of the present utility model is: described fore filter is made of Zeo-karb device and mixture iron exchange resin device, perhaps is made of the mixture iron exchange resin device; Described post-filter is composed in series by resin catcher and accurate filter, and the exit end of resin catcher is connected with the inlet end of accurate filter.
A kind of embodiment of the present utility model is: the inlet end junction at one of preposition output loop and fore filter is provided with recycle pump; Be provided with boosting pump at two of rearmounted output loop with the inlet end junction of Nuclear power plants secondary circuit vapour generator.
A kind of embodiment of the present utility model is: the structural shape that described accurate filter adopts non-recoil to wash, comprise vertical or horizontal filter, and its inlet end and exit end respectively are provided with tensimeter; This accurate filter comprises housing and filter core two portions, and filter core is a tubular structure, places enclosure interior.
A kind of embodiment of the present utility model is: described filter core is covered or is wrapped on the hard skeleton by high molecule plastic or silvalin and constitutes, or is made of the stainless (steel) wire braided tube; The filtering accuracy of filter core can be selected as required less than 80 μ m, generally adopts the filter core of about 40 μ m; Described shell material can be made of stainless steel or carbon steel liner rubber.
A kind of embodiment of the present utility model is: described hard skeleton is made of metal or non-metallic material.A kind of embodiment of the present utility model is: the inlet end of described fore filter and post-filter and exit end respectively are equipped with valve.
A kind of embodiment of the present utility model is: the granularity of being taken out of when described resin catcher can be removed condensed water through the processing of mixture iron exchange resin device is greater than the broken resin of 0.2mm, when preventing that mixture iron exchange resin device water cap from damaging, a large amount of resins bleed in the condensed water.Described accurate filter is not separated granularity in the condensed water with other solids by the broken resin that resin catcher is removed less than 0.2mm by filter element filtering with condensed water; When accurate filter import and export tensimeter reached the pressure reduction of setting, the expression filter core state that reaches capacity needed more renew cartridge.
The utlity model has following beneficial effect:
The utility model is owing to be provided with post-filter at secondary circuit, therefore, not only can catch the broken resin of macrobead that condensed water spills after prefiltration is handled, the granularity that resin catcher can not can also be captured is less than broken resin of the small-particle of 0.2mm and graininess impurity, avoid these broken resins to enter secondary circuit and under hot conditions, decompose the generation sulfate ion, cause the secondary circuit sulfate ion concentration excessive, cause at the position, slit of vapour generator and concentrate, form the acid attack environment, bring out the corrosion failure phenomenon of steam generator heat-transfer pipe, have the nuclear power station steam generator of preventing sulfate radical and exceed standard, reach and guarantee the be not broken beneficial effect of resin stain of secondary circuit water quality.
Description of drawings
Fig. 1 is a structural representation of the present utility model.
Embodiment
Specific embodiment 1
Fig. 1 constitutes specific embodiment of the utility model 1.
With reference to Fig. 1, present embodiment comprises fore filter 1, post-filter 2, recycle pump 3, condensate booster pump 4; The inlet end of fore filter 1 is connected with the condensed water delivery port of the main condensate pump of nuclear power station steam generator, the exit end of fore filter 1 is divided into two tunnel preposition output loops, and one of preposition output loop is connected with the inlet end of fore filter 1, two being connected with the inlet end of post-filter 2 of preposition output loop; The exit end of post-filter 2 is divided into two tunnel rearmounted output loops, and one of rearmounted output loop is connected with the inlet end of fore filter 1, and two of rearmounted output loop is connected with the inlet end of Nuclear power plants secondary circuit vapour generator.
The characteristics of present embodiment are: described fore filter 1 comprises Zeo-karb device 1-1 and mixture iron exchange resin device 1-2; Described post-filter 2 comprises resin catcher 2-1 and accurate filter 2-2.
The condensed water delivery port of main condensate pump is connected with the inlet end of Zeo-karb device 1-1, the exit end one tunnel of Zeo-karb device 1-1 connects the inlet end of mixture iron exchange resin device 1-2, another road is connected with recycle pump 3, reenters Zeo-karb device 1-1 and filter under its effect; The exit end one tunnel of mixture iron exchange resin device 1-2 is connected with the inlet end of resin catcher 2-1 after the exit end of resin catcher 2-1 is connected with the inlet end of accurate filter 2-2, another road is connected with recycle pump 3, reenters mixture iron exchange resin device 1-2 and filter under its effect; The exit end one tunnel of recycle pump 3 is connected with the inlet end of Zeo-karb device 1-1, and one the tunnel is connected with the inlet end of mixture iron exchange resin device 1-2; The exit end one tunnel of accurate filter 2-2 is connected with the inlet end of Zeo-karb device 1-1, and one the tunnel is connected through the inlet end of condensate booster pump 4 with Nuclear power plants secondary circuit vapour generator; Inlet end and the exit end of described Zeo-karb device 1-1, mixture iron exchange resin device 1-2, resin catcher 2-1 and accurate filter 2-2 all are equipped with valve 5.
Wherein accurate filter 2-2 adopts the pattern that non-recoil is washed, and can be vertical or horizontal filter, and its inlet end and exit end are equipped with tensimeter; Accurate filter 2-2 contains housing 2-2-1 and filter core 2-2-2 two portions.Housing 2-2-1 material can adopt stainless steel or carbon steel liner rubber; Filter core 2-2-2 is covered or is twined the hard skeleton that metal or non-metallic material constitute and constitutes by high molecule plastic or silvalin, perhaps be made of the stainless (steel) wire braided tube; The filtering accuracy of filter core 2-2-2 can be selected as required less than 80 μ m, generally adopts the filter core of about 40 μ m, and when accurate filter import and export tensimeter reached the pressure reduction of setting, the expression filter core state that reaches capacity needed more renew cartridge.
When the effusive condensed water of main condensate pump is up-to-standard, need not filter and flow directly into Nuclear power plants secondary circuit vapour generator.If defective, condensed water is introduced into Zeo-karb device 1-1 and filters, and removes dissolved cation impurity and graininess impurity in the condensed water, and its water outlet enters mixture iron exchange resin device 1-2 and filters, and removes positively charged ion, anionic impurity; The water outlet of mixture iron exchange resin device is after resin catcher 2-1 removes oarse-grained broken resin, condensed water inflow accurate filter 2-2 removes the impurity such as short grained resin chips in the condensed water, guarantees sulfate radical and overall water quality requirement in the secondary circuit water.Wherein Zeo-karb device 1-1 and mixture iron exchange resin device 1-2 can be provided with according to self under the effect of recycle pump 3, when the water quality control that does not reach setting in condensed water requires, open respective valves 5, automated cycle reenters Zeo-karb device 1-1 or mixture iron exchange resin device 1-2 filtration under the effect of recycle pump 3 and condensate booster pump 4.
The characteristics of present embodiment are: described fore filter 1 comprises mixture iron exchange resin device 1-2.Other are identical with specific embodiment 1.
Claims (8)
1. be used for the smart filtration filtering system of nuclear power station steam generator, it is characterized in that: comprise fore filter (1) and post-filter (2); The inlet end of fore filter (1) is connected with the condensed water delivery port of the main condensate pump of nuclear power station steam generator, the exit end of fore filter (1) is divided into two tunnel preposition output loops, and one of preposition output loop is connected with the inlet end of fore filter (1), two being connected with the inlet end of post-filter (2) of preposition output loop; The exit end of post-filter (2) is divided into two tunnel rearmounted output loops, and one of rearmounted output loop is connected with the inlet end of fore filter (1), and two of rearmounted output loop is connected with the inlet end of Nuclear power plants secondary circuit vapour generator.
2. the smart filtration filtering system that is used for nuclear power station steam generator according to claim 1, it is characterized in that: described fore filter (1) is made of Zeo-karb device (1-1) and mixture iron exchange resin device (1-2), perhaps is made of mixture iron exchange resin device (1-2).
3. the smart filtration filtering system that is used for nuclear power station steam generator according to claim 1 is characterized in that: the inlet end junction at one of preposition output loop and fore filter (1) is provided with recycle pump (3).
4. the smart filtration filtering system that is used for nuclear power station steam generator according to claim 1 and 2, it is characterized in that: described post-filter (2) is composed in series by resin catcher (2-1) and accurate filter (2-2), and the exit end of resin catcher (2-1) is connected with the inlet end of accurate filter (2-2).
5. the smart filtration filtering system that is used for nuclear power station steam generator according to claim 1 and 2 is characterized in that: be provided with boosting pump (4) at two of rearmounted output loop with the inlet end junction of Nuclear power plants secondary circuit vapour generator.
6. the smart filtration filtering system that is used for nuclear power station steam generator according to claim 4, it is characterized in that: the structural shape that described accurate filter (2-2) adopts non-recoil to wash, comprise vertical or horizontal filter, its inlet end and exit end respectively are provided with tensimeter; This accurate filter comprises housing (2-2-1) and filter core (2-2-2) two portions, and filter core (2-2-2) is a tubular structure, places housing (2-2-1) inside.
7. the smart filtration filtering system that is used for nuclear power station steam generator according to claim 6 is characterized in that: described filter core (2-2-2) is covered or is wrapped on the hard skeleton by high molecule plastic or silvalin and constitutes, or is made of the stainless (steel) wire braided tube; The filtering accuracy of filter core (2-2-2) is less than 80 μ m; Described housing (2-2-1) is made of stainless steel or carbon steel liner rubber.
8. the smart filtration filtering system that is used for nuclear power station steam generator according to claim 1 and 2 is characterized in that: the inlet end and the exit end of described fore filter (1) and post-filter (2) respectively are equipped with valve (5).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009200583851U CN201648058U (en) | 2009-06-12 | 2009-06-12 | Fine filter system for steam generator of nuclear power station |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009200583851U CN201648058U (en) | 2009-06-12 | 2009-06-12 | Fine filter system for steam generator of nuclear power station |
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| CN201648058U true CN201648058U (en) | 2010-11-24 |
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| CN2009200583851U Expired - Fee Related CN201648058U (en) | 2009-06-12 | 2009-06-12 | Fine filter system for steam generator of nuclear power station |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102161542A (en) * | 2011-03-14 | 2011-08-24 | 华电水处理技术工程有限公司 | Method and device for precisely processing nuclear power station condensation water |
| CN103177781A (en) * | 2011-12-23 | 2013-06-26 | 江苏核电有限公司 | Method for controlling concentration of sulfate radical of pressurized water reactor nuclear power plant unit-loop |
| CN106404431A (en) * | 2015-08-10 | 2017-02-15 | 核动力运行研究所 | Steam generator blowdown testing device |
| CN111302539A (en) * | 2020-02-17 | 2020-06-19 | 杨霞 | Condensate water circulating device for nuclear power station |
| CN111777237A (en) * | 2020-07-10 | 2020-10-16 | 三门核电有限公司 | Purification method for nuclear power plant evaporator sewage discharge system |
-
2009
- 2009-06-12 CN CN2009200583851U patent/CN201648058U/en not_active Expired - Fee Related
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102161542A (en) * | 2011-03-14 | 2011-08-24 | 华电水处理技术工程有限公司 | Method and device for precisely processing nuclear power station condensation water |
| CN102161542B (en) * | 2011-03-14 | 2012-12-26 | 华电水务工程有限公司 | Method and device for precisely processing nuclear power station condensation water |
| CN103177781A (en) * | 2011-12-23 | 2013-06-26 | 江苏核电有限公司 | Method for controlling concentration of sulfate radical of pressurized water reactor nuclear power plant unit-loop |
| CN103177781B (en) * | 2011-12-23 | 2015-08-26 | 江苏核电有限公司 | A kind of pressurized-water reactor nuclear power plant unit primary Ioops sulfate concentration control method |
| CN106404431A (en) * | 2015-08-10 | 2017-02-15 | 核动力运行研究所 | Steam generator blowdown testing device |
| CN106404431B (en) * | 2015-08-10 | 2019-04-16 | 核动力运行研究所 | A kind of steam generator blowdown experimental rig |
| CN111302539A (en) * | 2020-02-17 | 2020-06-19 | 杨霞 | Condensate water circulating device for nuclear power station |
| CN111302539B (en) * | 2020-02-17 | 2020-12-15 | 钱小英 | Condensate water circulating device for nuclear power station |
| CN111777237A (en) * | 2020-07-10 | 2020-10-16 | 三门核电有限公司 | Purification method for nuclear power plant evaporator sewage discharge system |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C56 | Change in the name or address of the patentee |
Owner name: CHINA ENERGY ENGINEERING GROUP GUANGDONG ELECTRIC Free format text: FORMER NAME: GUANGDONG ELECTRIC POWER DESIGN INSTITUTE Owner name: CHINA ENERGY ENGINEERING GROUP GUANGDONG ELECTRIC Free format text: FORMER NAME: CHINA ENERGY ENGINEERING GROUP GUANGDONG ELECTRIC POWER DESIGN INSTITUTE |
|
| CP01 | Change in the name or title of a patent holder |
Address after: 510080 No. 846 Dongfeng East Road, Guangdong, Guangzhou Patentee after: CHINA ENERGY ENGINEERING GROUP GUANGDONG ELECTRIC POWER DESIGN INSTITUTE Co.,Ltd. Address before: 510080 No. 846 Dongfeng East Road, Guangdong, Guangzhou Patentee before: GUANGDONG ELECTRIC POWER DESIGN INSTITUTE OF CHINA ENERGY ENGINEERING GROUP Co.,Ltd. Address after: 510080 No. 846 Dongfeng East Road, Guangdong, Guangzhou Patentee after: GUANGDONG ELECTRIC POWER DESIGN INSTITUTE OF CHINA ENERGY ENGINEERING GROUP Co.,Ltd. Address before: 510080 No. 846 Dongfeng East Road, Guangdong, Guangzhou Patentee before: Guangdong Electric Power Design Institute |
|
| C56 | Change in the name or address of the patentee | ||
| CP02 | Change in the address of a patent holder |
Address after: 510670 Luogang District, Guangdong, Guangzhou Science City Fung Road, No. 1, No. Patentee after: CHINA ENERGY ENGINEERING GROUP GUANGDONG ELECTRIC POWER DESIGN INSTITUTE Co.,Ltd. Address before: 510080 No. 846 Dongfeng East Road, Guangdong, Guangzhou Patentee before: CHINA ENERGY ENGINEERING GROUP GUANGDONG ELECTRIC POWER DESIGN INSTITUTE Co.,Ltd. |
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| CF01 | Termination of patent right due to non-payment of annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20101124 Termination date: 20170612 |