CN210511614U - Flexible tube plate structure for steam generator of nuclear power station - Google Patents
Flexible tube plate structure for steam generator of nuclear power station Download PDFInfo
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- CN210511614U CN210511614U CN201921152333.0U CN201921152333U CN210511614U CN 210511614 U CN210511614 U CN 210511614U CN 201921152333 U CN201921152333 U CN 201921152333U CN 210511614 U CN210511614 U CN 210511614U
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- tube plate
- thermal expansion
- steam generator
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- inner cylinder
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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
Abstract
The utility model relates to a flexible tube plate structure for a nuclear power station steam generator, which comprises a thermal expansion buffer section and an elastic tube plate, wherein the two ends of the elastic tube plate are connected with the thermal expansion buffer section through a transition section; the thermal expansion buffer section is integrally cylindrical and consists of an inner cylinder, an outer cylinder and a connecting flange, wherein the inner cylinder and the outer cylinder are different in thickness, a cavity serving as a fluid dead zone is formed between the inner cylinder and the outer cylinder, two ends of the connecting flange are respectively welded with one end of the inner cylinder and one end of the outer cylinder, the other end of the inner cylinder is welded with the end part of the transition section, and the side wall of the other end of the outer cylinder is; the elastic tube plate and the transition section are formed by one-time forging, the transition section is an arc-shaped revolving body, and heat exchange tube holes are uniformly and densely distributed on the elastic tube plate; the effective thicknesses of the elastic tube plate, the transition section and the inner cylinder of the thermal expansion buffer section are equal. The structure can reduce the thickness of the tube plate, reduce the thermal stress at two sides of the tube plate, and the tube plate has certain elasticity, and can absorb the thermal expansion difference between the heat exchange tube and the steam generator cylinder to a certain degree.
Description
Technical Field
The utility model relates to a nuclear power station evaporimeter technical field, in particular to flexible tube sheet structure for nuclear power station steam generator.
Background
A shell-and-tube steam generator is mainly used as a steam generator in the nuclear power industry, and a steam generator tube plate is one of important parts of the steam generator. The steam generator of the nuclear power station has harsh working conditions, the design temperature of a steam outlet tube plate can reach 660 ℃, the design pressure can reach 18MPa, and the high-pressure nuclear power station can bear high pressure, high temperature and medium erosion. The traditional rigid tube plate needs to increase the thickness of the tube plate to bear higher pressure load, and needs to be thinner and better to reduce the influence of temperature difference thermal stress, so that the integration of high temperature and high pressure is difficult to realize. Therefore, it is necessary to design a flexible tube plate structure of a steam generator in a nuclear power plant, so that the flexible tube plate structure can bear the combined action of high temperature and high pressure.
SUMMERY OF THE UTILITY MODEL
The utility model aims to solve the technical problem that a flexible tube sheet structure of nuclear power steam generator is provided, this tube sheet structure can provide good solution for work at high temperature, highly compressed steam generator export tube sheet.
The utility model provides a technical scheme that above-mentioned technical problem took is:
the utility model provides a flexible tube plate structure for a nuclear power station steam generator, which is characterized by comprising a thermal expansion buffer section and an elastic tube plate, wherein two ends of the elastic tube plate are connected with the thermal expansion buffer section through a transition section; the thermal expansion buffer section is integrally cylindrical and comprises an inner cylinder, an outer cylinder and a connecting flange, wherein the inner cylinder, the outer cylinder and the connecting flange are different in thickness, a cavity serving as a fluid dead zone is formed between the inner cylinder and the outer cylinder, two ends of the connecting flange are respectively welded with one end of the inner cylinder and one end of the outer cylinder, the other end of the inner cylinder is welded with the end part of the transition section, and the side wall of the other end of the outer cylinder is welded with a barrel of a steam generator; the elastic tube plate and the transition section are formed by one-time forging, the transition section is an arc-shaped revolving body, and heat exchange tube holes are uniformly and densely distributed in the elastic tube plate; the effective thicknesses of the elastic tube plate, the transition section and the inner cylinder of the thermal expansion buffer section are equal.
Further, the length of the inner cylinder in the thermal expansion buffer section is greater than that of the outer cylinder.
Furthermore, the length of a minimum straight edge required by butt welding of the inner cylinder in the transition section and the thermal expansion buffer section is 25-50 mm.
Furthermore, the connecting flange is formed by integrally forming a short arm section and a long arm section, and one end of the short arm and one end of the long arm are respectively welded with one end of the inner cylinder and one end of the outer cylinder in the thermal expansion buffering section.
Further, the difference between the lengths of the short arm and the long arm of the connecting flange is not less than 50 mm.
Further, a cavity formed between the inner cylinder and the outer cylinder is filled with a heat insulating material.
The flexible tube plate structure has the advantages of being capable of bearing high pressure, high temperature and high temperature difference, having certain elasticity, absorbing the thermal expansion difference of the heat exchange tube and the steam generator cylinder body, and reducing the thermal stress caused by the temperature difference.
The utility model has the advantages that:
1. the thickness of the related flexible tube plate is reduced by about 2/3 compared with that of the common rigid tube plate, the thermal bending stress caused by the temperature difference of the two sides of the tube plate is obviously reduced, and the cost of the nuclear-grade forge piece is effectively saved;
2. through a fluid dead zone formed by the inner barrel and the outer barrel of the thermal expansion buffer section or the fluid dead zone and a built-in heat insulation material thereof, thermal impact of hot fluid in a space enclosed by the inner barrel and the elastic tube plate of the buffer section on the outer barrel and the barrel of the buffer section can be effectively isolated, so that the design temperature of the barrel is reduced, and the design economy of the barrel is improved; in addition, the combination of the elastic tube plate and the thermal expansion buffer section increases the flexibility of the whole structure, the thermal expansion difference between the heat exchange tube and the cylinder can be automatically compensated, and compensation elements such as expansion joints and the like do not need to be arranged.
3. The folding edge section of the flexible tube plate adopts semicircular arc transition, the structure is simple, the forging and the inspection are convenient, the flexible tube plate is in butt welding with the hot sleeve inner cylinder, and the structural reliability is high.
Drawings
Fig. 1 is a schematic view of the connection of the flexible tube sheet with the heat exchange tube and the steam generator cylinder according to the present invention.
The symbols in the drawings illustrate that:
1-thermal expansion buffer section
11-inner cylinder 12-outer cylinder 13-connecting flange
2-transition section
3-elastic tube plate
4-steam generator cylinder
5-heat exchange tube.
Detailed Description
The flexible tube sheet of the present invention is further described below with reference to the accompanying drawings.
Please refer to fig. 1, which is a schematic structural diagram of the connection between the flexible tube plate and the heat exchange tube and the steam generator cylinder of the present invention, the flexible tube plate structure for the steam generator of the nuclear power station is used for the heat steam outlet tube plate of the steam generator of the nuclear power station, the steam generator of the nuclear power station is used for the steam generator of the primary loop and the secondary loop, the design pressure can reach 18MPa, and the design temperature can reach 660 ℃. The flexible tube plate structure of the embodiment comprises a thermal expansion buffer section 1 and an elastic tube plate 3, wherein the thermal expansion buffer section 1 is connected with the elastic tube plate 3 through a transition section 2. The thermal expansion buffer section 1 is integrally cylindrical and consists of inner and outer cylinders (11 and 12) with different thicknesses and a connecting flange 13, a cavity is formed between the inner and outer cylinders, the cavity is a fluid dead zone, and thermal shock of thermal fluid in a space enclosed by the inner cylinder 11 of the buffer section and the elastic tube plate 3 to the outer cylinder 12 of the buffer section and the steam generator cylinder 4 can be effectively isolated through the cavity or the cavity and a built-in thermal insulation material thereof, so that the design temperature of the cylinder is reduced, and the design economy of the cylinder is improved; the connecting flange 13 is formed by integrally forming a short arm section and a long arm section, one end of the inner cylinder 11 is welded with one end of the transition section 2, the other end of the inner cylinder 11 is welded with one end of the connecting flange 13, the other end of the connecting flange 13 is welded with one end of the outer cylinder 12, and the side wall of the other end of the outer cylinder 12 is welded with the steam generator cylinder 4; the connecting flange 13 is used for connecting an external hot gas conduit of the steam generator (the pipeline is not shown in the figure), besides the internal cylinder and the external cylinder, wherein a short arm section of the connecting flange 13 is used for connecting the external hot gas conduit of the steam generator with the external cylinder 12, and a long arm section of the connecting flange 13 is used for connecting the internal cylinder 11 with the external hot gas conduit of the steam generator. The elastic tube plate 3 and the transition sections 2 at two ends of the elastic tube plate are formed by one-time forging, the transition sections 2 are arc-shaped revolution bodies, heat exchange tube holes are uniformly and densely distributed (for example, in a regular triangle tube distribution mode) on the elastic tube plate 3, and the heat exchange tubes 5 penetrate through the tube holes of the elastic tube plate 3 and are welded and fixed; the effective thicknesses of the elastic tube plate 3, the transition section 2 and the inner cylinder 11 of the thermal expansion buffer section are equal. The structure can reduce the thickness of the tube plate and reduce the temperature difference stress on two sides of the tube plate, so that the tube plate has certain elasticity, can absorb the thermal expansion difference between the heat exchange tube 5 and the steam generator barrel 4 to a certain degree, and is particularly suitable for nuclear power steam generators at high temperature and high pressure.
The utility model discloses well elasticity tube sheet 3, changeover portion 2 and 11 three's in thermal energy buffering section inner tube effective thickness equals, and this effective thickness's minimum delta calculates according to following formula:
wherein:
d is the maximum circumcircle diameter of the elastic tube plate 3, mm;
Pa——calculated load (pressure) of the elastic tube sheet 3, MPa;
And the corner radius of the transition section 2 is not less than 1/8d, so that the strength of the elastic tube plate 3, the transition section 2 and the thermal expansion buffer section inner barrel 11 are similar to ensure the flexibility of the whole tube plate.
Referring to fig. 1, L1 in the figure is used to indicate the minimum straight edge length required by butt welding of the inner cylinder 11 in the transition section 2 and the thermal expansion buffer section 1, and is 25-50 mm; l2 is the total height of the elastic tube sheet and the transition section 2; l3 is the total length of the inner tube 11 in the thermal expansion buffer section 1; l4 is the total length of the outer tube 12 in the thermal expansion buffering section 1; l5 is the length of the long arm of the attachment flange 13; l6 is the short arm length of the attachment flange 13. L2 was determined from the elastic tube sheet 3 thickness and L1; in order to further absorb the thermal expansion difference between the heat exchange tube 5 and the steam generator cylinder 4, the length L3 of the inner cylinder 11 in the thermal expansion buffer section 1 is greater than the length L4 of the outer cylinder 12, and the lengths of L3 and L4 are not less than
The longer the length is, the better the length is according to the actual requirement; the length difference between L5 and L6 is not less than 50 mm.
On the basis of the scheme, the flexible tube plate of the utility model is formed by forging pieces through machining and welding, and is a conventional machining process in the field.
The working principle of the flexible tube plate structure is as follows:
the flexible tube plate structure forms a chamber on one side through the structures of the elastic tube plate 3, the thermal expansion buffer section 1 and the steam generator barrel 4 which are welded with each other, the elastic tube plate 3 is welded with the heat exchange tube 5 in a strength manner, and the inside of the heat exchange tube 5 and the inner surfaces of the elastic tube plate 3, the transition section 2 and the inner tube 11 of the thermal expansion buffer section form a chamber on the other side, so that the separation of cold and hot fluids is realized. When the flexible tube plate structure bears the combined action of pressure, temperature and heat exchange tube load, the elastic tube plate 3 generates flexible bending deformation to release the thermal stress caused by partial thermal expansion, meanwhile, continuous primary and secondary stress is generated in the transition section 2 and the inner tube 11 of the thermal expansion buffer section 1 to perform deformation coordination on the deformation of the elastic tube plate 3, and a cavity or a cavity between the inner tube 11 and the outer tube 12 of the thermal expansion buffer section and a heat insulating material arranged in the cavity or the cavity can effectively isolate thermal shock of hot fluid in a space enclosed by the inner tube 11 of the buffer section and the elastic tube plate 3 to the outer tube 12 of the thermal expansion buffer section and the steam generator tube 4, so that the outer tube 12 of the thermal expansion buffer section only bears the primary stress and a small amount of thermal bending stress generated by pressure. The deformation coordination between the inner cylinder 11 of the thermal expansion buffer section and the outer cylinder 12 of the thermal expansion buffer section is accomplished by a connecting flange 13.
Although embodiments of the present invention have been shown and described, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations of the above embodiments may be made by those of ordinary skill in the art without departing from the scope of the present invention, the scope of which is defined by the appended claims and their equivalents.
Claims (6)
1. A flexible tube plate structure for a steam generator of a nuclear power station is characterized by comprising a thermal expansion buffer section and an elastic tube plate, wherein two ends of the elastic tube plate are connected with the thermal expansion buffer section through a transition section; the thermal expansion buffer section is integrally cylindrical and comprises an inner cylinder, an outer cylinder and a connecting flange, wherein the inner cylinder, the outer cylinder and the connecting flange are different in thickness, a cavity serving as a fluid dead zone is formed between the inner cylinder and the outer cylinder, two ends of the connecting flange are respectively welded with one end of the inner cylinder and one end of the outer cylinder, the other end of the inner cylinder is welded with the end part of the transition section, and the side wall of the other end of the outer cylinder is welded with a barrel of a steam generator; the elastic tube plate and the transition section are formed by one-time forging, the transition section is an arc-shaped revolving body, and heat exchange tube holes are uniformly and densely distributed in the elastic tube plate; the effective thicknesses of the elastic tube plate, the transition section and the inner cylinder of the thermal expansion buffer section are equal.
2. The flexible tube sheet structure for a steam generator in a nuclear power plant as claimed in claim 1, wherein the length of the inner barrel in the thermal expansion buffering section is greater than the length of the outer barrel.
3. The flexible tube plate structure for the steam generator in the nuclear power station as claimed in claim 1, wherein the length of the minimum straight edge required for butt welding the transition section and the inner cylinder in the thermal expansion buffer section is 25-50 mm.
4. The flexible tube sheet structure for a steam generator in a nuclear power plant as claimed in claim 1, wherein the connecting flange is integrally formed by a short arm section and a long arm section, and one end of each of the short arm and the long arm is welded to one end of an inner tube and one end of an outer tube in the thermal expansion buffer section, respectively.
5. The flexible tube sheet structure for a steam generator in a nuclear power plant as claimed in claim 4, wherein the difference in length between the short arm and the long arm of the connection flange is not less than 50 mm.
6. The flexible tube sheet structure for a steam generator in a nuclear power plant according to any one of claims 1 to 5, wherein a heat insulating material is filled in a cavity formed between the inner cylinder and the outer cylinder.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201921152333.0U CN210511614U (en) | 2019-07-22 | 2019-07-22 | Flexible tube plate structure for steam generator of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201921152333.0U CN210511614U (en) | 2019-07-22 | 2019-07-22 | Flexible tube plate structure for steam generator of nuclear power station |
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| CN210511614U true CN210511614U (en) | 2020-05-12 |
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| CN201921152333.0U Active CN210511614U (en) | 2019-07-22 | 2019-07-22 | Flexible tube plate structure for steam generator of nuclear power station |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110345464A (en) * | 2019-07-22 | 2019-10-18 | 中核能源科技有限公司 | A kind of nuclear power station steam generator flexible tubesheet structure |
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2019
- 2019-07-22 CN CN201921152333.0U patent/CN210511614U/en active Active
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110345464A (en) * | 2019-07-22 | 2019-10-18 | 中核能源科技有限公司 | A kind of nuclear power station steam generator flexible tubesheet structure |
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