CN102032551A - Steam-water anti-scour device for nuclear power heater - Google Patents
Steam-water anti-scour device for nuclear power heater Download PDFInfo
- Publication number
- CN102032551A CN102032551A CN 201010540397 CN201010540397A CN102032551A CN 102032551 A CN102032551 A CN 102032551A CN 201010540397 CN201010540397 CN 201010540397 CN 201010540397 A CN201010540397 A CN 201010540397A CN 102032551 A CN102032551 A CN 102032551A
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- nuclear power
- end plate
- porous flash
- carbonated drink
- power heater
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Abstract
The invention discloses a steam-water anti-scour device for a nuclear power heater. The device is provided with a high-pressure heater with a drain inlet, and is characterized in that: a heat-insulating sleeve joint is arranged at the drain inlet of the high-pressure heater and is connected with an inner porous flash evaporation tube; an outer porous flash evaporation tube is sleeved outside the inner porous flash evaporation tube; and a front sealing end plate and a rear sealing end plate are fixedly connected to the two ends of the inner porous flash evaporation tube and the two ends of the outer porous flash evaporation tube. The device has a simple and reliable structure and a reasonable design, and is particularly suitable for a high-flow drain anti-scour design.
Description
Technical field
The present invention relates to a kind of high-pressure heater of nuclear power plant, relate in particular to the dewatering capacity-enlarging protection against erosion control technology of the high-pressure heater of the horizontal layout of nuclear power plant.
Background technology
All adopt the upper level height to add to add cascaded drain in large-scale unit mesohigh heater condensate system at present and arrange to the next stage height, thus the afterbody height to add the hydrophobic flow of acceptance just quite big.
For energy-saving and emission-reduction, the present domestic large nuclear-power unit of falling over each other to build.With respect to the large electric power plant unit, the characteristics of nuclear power generating sets are low parameters, big flow, demanding again reliability and long-life simultaneously.Therefore require the hydrophobic checking motion of a kind of high reliability of design, hydrophobic with the high energy of accepting big flow, avoid height to add housing or phenomenon appears washing away in heat-exchanging tube bundle, finally cause height to add and occur damaging, with the safe operation of induced damage resistive nuclear power generating sets.
Summary of the invention
It is simple relatively to the objective of the invention is to design a kind of structure, and dependable performance can adapt to the carbonated drink checking motion of nuclear power heater.
Above-mentioned technical problem of the present invention is mainly solved by following technical proposals: a kind of carbonated drink checking motion of nuclear power heater, has high-pressure heater, described high-pressure heater is provided with hydrophobic import, it is characterized in that: in the hydrophobic import department of described high-pressure heater, collet tubular type joint is installed, be connected with internal layer porous flash pipe on the joint, outside internal layer porous flash pipe, be set with outer porous flash pipe.
Technical scheme of the present invention can also be further perfect:
As preferably, be fixedly connected with front sealing end plate and rear seal end plate at internal layer porous flash pipe and outer porous flash pipe two ends.
As preferably, on the rear seal end plate, support member is housed.
As preferably, between rear seal end plate and high-pressure heater housing, be fixed with spacing leading truck.
As preferably, described connection is welding.
The invention has the beneficial effects as follows:
The high energy of big flow hydrophobic through multistage flash evaporation with after carbonated drink is separated, carbonated drink gently enters heat-exchanging tube bundle, it is simple in structure, dependable performance is easily manufactured.
Description of drawings
Accompanying drawing 1 is a kind of structural representation of the present invention;
Accompanying drawing 2 is A portion enlarged drawings.
Description of reference numerals: B, high-pressure heater, 1, casing joint, 2, internal layer porous flash pipe, 3, preceding Seal end plate, 4, outer porous flash pipe, 5, the back Seal end plate, 6, support member, 7 spacing leading trucks.
The specific embodiment
Below by embodiment also in conjunction with the accompanying drawings, technical scheme of the present invention is further described in detail.
Embodiment:
The carbonated drink checking motion of nuclear power heater as shown in Figure 1, 2, hydrophobic import department at high-pressure heater B installs a heat insulation casing joint 1 earlier, the high energy that reception upper level height adds is hydrophobic, and casing joint can be alleviated the heat fatigue of joint, increases the reliability that joint connects; Again according to the size of hydrophobic flow, the internal layer porous flash pipe 2 of a suitable porous type of design, this internal layer porous flash pipe is used anti-stainless steel material manufacturing of washing away, and weld with thermal sleeve, outside inner sleeve, design a suitably outer flash distillation antipriming pipe 4 of size again, this flash distillation antipriming pipe is also used anti-stainless steel material manufacturing of washing away, respectively weld a preceding Seal end plate 3 and back Seal end plate 5 at the two ends of internal layer porous flash pipe 2 and outer flash distillation antipriming pipe 4, form the flash distillation expansion space of two relative closure porous.The support member 6 that supports whole checking motion is housed on the Seal end plate 5 in the back and is fixed on height and add spacing leading truck 7 on the housing.
Adopt the hydrophobic erosion control structure of said structure,, do not worry that all washing away height after the hydrophobic flash distillation adds housing or heat-exchanging tube bundle, can guarantee that height adds safe and stable operation no matter how hydrophobic flow changes.
Claims (5)
1. the carbonated drink checking motion of a nuclear power heater, has high-pressure heater, described high-pressure heater is provided with hydrophobic import, it is characterized in that: in the hydrophobic import department of described high-pressure heater, collet tubular type joint is installed, be connected with internal layer porous flash pipe on the joint, outside internal layer porous flash pipe, be set with outer porous flash pipe.
2. the carbonated drink checking motion of nuclear power heater according to claim 1 is characterized in that: be fixedly connected with front sealing end plate and rear seal end plate at internal layer porous flash pipe and outer porous flash pipe two ends.
3. the carbonated drink checking motion of nuclear power heater according to claim 1 and 2 is characterized in that: on the rear seal end plate support member is housed.
4. the carbonated drink checking motion of nuclear power heater according to claim 1 and 2 is characterized in that: be fixed with spacing leading truck between rear seal end plate and high-pressure heater housing.
5. the carbonated drink checking motion of nuclear power heater according to claim 1 and 2 is characterized in that: described connection is welding.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201010540397 CN102032551A (en) | 2010-11-12 | 2010-11-12 | Steam-water anti-scour device for nuclear power heater |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201010540397 CN102032551A (en) | 2010-11-12 | 2010-11-12 | Steam-water anti-scour device for nuclear power heater |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN102032551A true CN102032551A (en) | 2011-04-27 |
Family
ID=43885801
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN 201010540397 Pending CN102032551A (en) | 2010-11-12 | 2010-11-12 | Steam-water anti-scour device for nuclear power heater |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102032551A (en) |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3610538A (en) * | 1968-08-07 | 1971-10-05 | Struthers Wells Corp | Diffuser for feed water heater |
| JPS54142402A (en) * | 1978-04-28 | 1979-11-06 | Toshiba Corp | Feed water heater |
| CN86102780A (en) * | 1985-04-24 | 1986-10-22 | 法国电力公司 | The feed water heater of steam generator |
| CN201203100Y (en) * | 2008-04-30 | 2009-03-04 | 南京汽轮电机集团泰兴宁兴机械有限公司 | Vertical heater of low dredging cold segment terminal difference |
| CN201866754U (en) * | 2010-11-12 | 2011-06-15 | 杭州锅炉集团股份有限公司 | Steam-water anti-scour device for nuclear electric heater |
-
2010
- 2010-11-12 CN CN 201010540397 patent/CN102032551A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3610538A (en) * | 1968-08-07 | 1971-10-05 | Struthers Wells Corp | Diffuser for feed water heater |
| JPS54142402A (en) * | 1978-04-28 | 1979-11-06 | Toshiba Corp | Feed water heater |
| CN86102780A (en) * | 1985-04-24 | 1986-10-22 | 法国电力公司 | The feed water heater of steam generator |
| CN201203100Y (en) * | 2008-04-30 | 2009-03-04 | 南京汽轮电机集团泰兴宁兴机械有限公司 | Vertical heater of low dredging cold segment terminal difference |
| CN201866754U (en) * | 2010-11-12 | 2011-06-15 | 杭州锅炉集团股份有限公司 | Steam-water anti-scour device for nuclear electric heater |
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| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C02 | Deemed withdrawal of patent application after publication (patent law 2001) | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20110427 |