CN201866754U - Steam-water anti-scour device for nuclear electric heater - Google Patents
Steam-water anti-scour device for nuclear electric heater Download PDFInfo
- Publication number
- CN201866754U CN201866754U CN201020602324XU CN201020602324U CN201866754U CN 201866754 U CN201866754 U CN 201866754U CN 201020602324X U CN201020602324X U CN 201020602324XU CN 201020602324 U CN201020602324 U CN 201020602324U CN 201866754 U CN201866754 U CN 201866754U
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- China
- Prior art keywords
- end plate
- porous flash
- nuclear power
- carbonated drink
- pressure heater
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
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Abstract
The utility model discloses a steam-water anti-scour device for a nuclear electric heater. The device is provided with a high pressure heater which is provided with a hydrophobic inlet, and is characterized in that: a heat insulating sleeve type joint is arranged at the hydrophobic inlet of the high pressure heater and is connected with an inner porous flash evaporation pipe; an outer porous flash evaporation pipe is sleeved outside the inner porous flash evaporation pipe; and the two ends of the inner porous flash evaporation pipe and the outer porous flash evaporation pipe are fixedly connected with a front sealing end plate and a rear sealing end plate. The device has a simple and reliable structure, is rational in design and is extremely suitable for high-flow hydrophobic anti-scour design.
Description
Technical field
The utility model relates to a kind of high-pressure heater of nuclear power plant, relates 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
The purpose of this utility model is that a kind of structure of design is simple relatively, and dependable performance can adapt to the carbonated drink checking motion of nuclear power heater.
Above-mentioned technical problem of the present utility model 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.
The technical solution of the utility model 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 beneficial effects of the utility model are:
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 utility model;
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, the technical solution of the utility model 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 |
|---|---|---|---|
| CN201020602324XU CN201866754U (en) | 2010-11-12 | 2010-11-12 | Steam-water anti-scour device for nuclear electric heater |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201020602324XU CN201866754U (en) | 2010-11-12 | 2010-11-12 | Steam-water anti-scour device for nuclear electric heater |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN201866754U true CN201866754U (en) | 2011-06-15 |
Family
ID=44137908
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201020602324XU Expired - Fee Related CN201866754U (en) | 2010-11-12 | 2010-11-12 | Steam-water anti-scour device for nuclear electric heater |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN201866754U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102032551A (en) * | 2010-11-12 | 2011-04-27 | 杭州锅炉集团股份有限公司 | Steam-water anti-scour device for nuclear power heater |
| CN106247313A (en) * | 2016-08-31 | 2016-12-21 | 东方电气集团东方锅炉股份有限公司 | A kind of U-shaped tube type pressure heater with flash distillation enforcing condensation heat transfer mechanism |
-
2010
- 2010-11-12 CN CN201020602324XU patent/CN201866754U/en not_active Expired - Fee Related
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102032551A (en) * | 2010-11-12 | 2011-04-27 | 杭州锅炉集团股份有限公司 | Steam-water anti-scour device for nuclear power heater |
| CN106247313A (en) * | 2016-08-31 | 2016-12-21 | 东方电气集团东方锅炉股份有限公司 | A kind of U-shaped tube type pressure heater with flash distillation enforcing condensation heat transfer mechanism |
| CN106247313B (en) * | 2016-08-31 | 2018-05-11 | 东方电气集团东方锅炉股份有限公司 | A kind of U-shaped tube type pressure heater with flash distillation enforcing condensation heat transfer mechanism |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| 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: 20110615 Termination date: 20181112 |