CN103871488A - Anti-vibration bar structure for steam generator of pressurized water reactor (PWR) nuclear power plant - Google Patents
Anti-vibration bar structure for steam generator of pressurized water reactor (PWR) nuclear power plant Download PDFInfo
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- CN103871488A CN103871488A CN201210538916.3A CN201210538916A CN103871488A CN 103871488 A CN103871488 A CN 103871488A CN 201210538916 A CN201210538916 A CN 201210538916A CN 103871488 A CN103871488 A CN 103871488A
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- steam generator
- vibrationproof bar
- vibrationproof
- power plant
- nuclear power
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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 relates to the technical field of bent pipe section bearing technology for PWR steam generator, and specifically discloses an anti-vibration bar for steam generator of PWR nuclear power plant. The anti-vibration bar structure comprises a plurality of anti-vibration bar assemblies arranged on the bent pipe section of a U-shaped thermal conductive pipe of a steam generator, each anti-vibration bar assembly is composed of a plurality of anti-vibration bars, the anti-vibration bars in the same group are arranged on the same level relative to the upper surface of a bearing plate arranged on the top part of the steam generator, and the length of the anti-vibration bars can be adjusted according to the different positions of the U-shaped thermal conductive pipe so as to make the overall contour of the end parts of all anti-vibration bars be smooth. The anti-vibration bar structure reduces the flow resistance of parts to a certain degree. The performances of the anti-vibration bar are better than those of second generation anti-vibration bar assemblies.
Description
Technical field
The invention belongs to PWR steam generator with heat-transfer pipe bend pipe pipeline section supporting technology field, be specifically related to a kind of vibrationproof bar for PWR nuclear power plant steam generator.
Background technology
Vertical, inverted-loop tube, natural circulation steam generator (hereinafter to be referred as SG) are the main flow SG patterns that domestic nuclear power plant adopts.The vibrationproof bar assembly that is positioned at heat-transfer pipe bend loss is the vitals that U-shaped pipe bend loss is provided to supporting, and the quality of its structural design will be related to fretting, stress corrosion and the heat transfer conditions of pipe.
In domestic two generations, add unit application vibrationproof bar assembly more widely, its vibrationproof bar end design comparison " coarse ", and end profile becomes " zigzag ".Simple process in design, makes vibrationproof bar end size long, has increased parts flow resistance.
Summary of the invention
The object of the present invention is to provide a kind of vibrationproof bar structure for PWR nuclear power plant steam generator, can realize the supporting to U-Shaped Tube for PWR Steam Generator bend loss, and in the to a certain degree individual flow resistance that reduces parts.
Technical scheme of the present invention is as follows: a kind of vibrationproof bar structure for PWR nuclear power plant steam generator, be included in the some groups of vibrationproof bar assemblies that install at the U-shaped heat-transfer pipe bend pipe pipeline section of steam generator place, every group of vibrationproof bar assembly is made up of several vibrationproof bars, vibrationproof bar in same group is arranged on sustained height with respect to steam generator top support plate upper surface, the length of vibrationproof bar is according to the position difference of U-shaped heat-transfer pipe and length difference, and makes the end profile entirety of all vibrationproof bars level and smooth.
The end tip of described vibrationproof bar is fixed with end cap, and described vibrationproof bar is welded and fixed by end cap and retaining ring, and keeps the end cap of every group of vibrationproof bar end to be positioned at the same side of retaining ring.
Described end cap length is 50mm, and described retaining ring xsect is square, and the length of side is 10mm, and retaining ring is welded on the point midway of the fixing end cap in vibrationproof bar end on the same group.
Between the outer U-shaped heat-transfer pipe of described steam generator, two pairs of maintaining items are also installed, and the two ends of maintaining item keep fixing by welding and retaining ring.
Described end cap is made up of nickel-base material; Described retaining ring is made up of nickel-base material.
Described maintaining item is made up of nickel-base material.
Described end cap is fixed on the end of vibrationproof bar end by two pins.
Remarkable result of the present invention is: a kind of vibrationproof bar structure for PWR nuclear power plant steam generator of the present invention, and it has reduced the flow resistance of parts to a certain extent, and various aspects of performance is better than existing two generations and adds unit vibrationproof bar assembly.
Brief description of the drawings
Fig. 1 is a kind of vibrationproof bar structural representation for PWR nuclear power plant steam generator of the present invention;
Fig. 2 is U-U sectional view in Fig. 1;
Fig. 3 is the partial enlarged drawing at A place in Fig. 1;
Fig. 4 is the partial enlarged drawing at B place in Fig. 2;
In figure: 1, U-shaped heat-transfer pipe; 2, vibrationproof bar; 3, end cap; 4, retaining ring; 5, maintaining item.
Embodiment
Below in conjunction with drawings and the specific embodiments, the present invention is described in further detail.
As shown in Fig. 1～4, a kind of vibrationproof bar structure for PWR nuclear power plant steam generator, be included in the some groups of vibrationproof bar assemblies that install at the U-shaped heat-transfer pipe of steam generator 1 bend pipe pipeline section place, every group of vibrationproof bar assembly is made up of several vibrationproof bars 2, wherein, vibrationproof bar 2 in one group is arranged on sustained height with respect to steam generator top support plate upper surface, the length of vibrationproof bar 2 is according to the position difference of U-shaped heat-transfer pipe 1 and length difference, and makes the end profile entirety of all vibrationproof bars 2 level and smooth; The end tip of each vibrationproof bar 2 is fixedly connected with by two pins the end cap 3 that nickel-base material is made, the retaining ring 4 that every group of vibrationproof bar 2 made by end cap 3 and nickel-base material is welded and fixed, and the end cap 3 that keeps every group of vibrationproof bar 2 ends is positioned at the same side of retaining ring 4, wherein, retaining ring 4 xsects can make square, and the length of side is 10mm; Each end cap 3 length are 50mm, and retaining ring 4 is welded on the point midway of each end cap 3.The maintaining item 5 of two pairs of nickel-base materials is also installed between the outer U-shaped heat-transfer pipe 1 of steam generator, and the two ends of maintaining item 5 keep fixing by welding and retaining ring 4.
Claims (7)
1. the vibrationproof bar structure for PWR nuclear power plant steam generator, be included in the some groups of vibrationproof bar assemblies that install at the U-shaped heat-transfer pipe of steam generator (1) bend pipe pipeline section place, every group of vibrationproof bar assembly is made up of several vibrationproof bars (2), it is characterized in that: the vibrationproof bar (2) in same group is arranged on sustained height with respect to steam generator top support plate upper surface, the length of vibrationproof bar (2) is according to the position difference of U-shaped heat-transfer pipe (1) and length difference, and makes the end profile entirety of all vibrationproof bars (2) level and smooth.
2. a kind of vibrationproof bar structure for PWR nuclear power plant steam generator according to claim 1, it is characterized in that: the end tip of described vibrationproof bar (2) is fixed with end cap (3), described vibrationproof bar (2) is welded and fixed by end cap (3) and retaining ring (4), and keeps the end cap (3) of every group of vibrationproof bar (2) end to be positioned at the same side of retaining ring (4).
3. a kind of vibrationproof bar structure for PWR nuclear power plant steam generator according to claim 2, it is characterized in that: described end cap (3) length is 50mm, described retaining ring (4) xsect is square, the length of side is 10mm, and retaining ring (4) is welded on the point midway of the fixing end cap (3) in vibrationproof bar (2) end on the same group.
4. a kind of vibrationproof bar structure for PWR nuclear power plant steam generator according to claim 1, it is characterized in that: between the described outer U-shaped heat-transfer pipe of steam generator (1), two pairs of maintaining items (5) are also installed, and the two ends of maintaining item (5) keep fixing by welding and retaining ring (4).
5. according to any one the vibrationproof bar structure for PWR nuclear power plant steam generator described in claim 1～3, it is characterized in that: described end cap (3) is made up of nickel-base material; Described retaining ring (4) is made up of nickel-base material.
6. a kind of vibrationproof bar structure for PWR nuclear power plant steam generator according to claim 4, is characterized in that: described maintaining item (5) is made up of nickel-base material.
7. any one vibrationproof bar structure for PWR nuclear power plant steam generator according to claim 1 and 2, is characterized in that: described end cap (3) is fixed on the end of vibrationproof bar (2) end by two pins.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210538916.3A CN103871488A (en) | 2012-12-13 | 2012-12-13 | Anti-vibration bar structure for steam generator of pressurized water reactor (PWR) nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210538916.3A CN103871488A (en) | 2012-12-13 | 2012-12-13 | Anti-vibration bar structure for steam generator of pressurized water reactor (PWR) nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN103871488A true CN103871488A (en) | 2014-06-18 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210538916.3A Pending CN103871488A (en) | 2012-12-13 | 2012-12-13 | Anti-vibration bar structure for steam generator of pressurized water reactor (PWR) nuclear power plant |
Country Status (1)
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| CN (1) | CN103871488A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107221357A (en) * | 2017-05-24 | 2017-09-29 | 四川行之智汇知识产权运营有限公司 | Heat exchanging chamber in integral vibration damping type reactor evaporator |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5447191A (en) * | 1993-08-20 | 1995-09-05 | Framatome | Heat exchanger including means for holding antivibration bars interposed between the tubes of the bundle of the exchanger |
| CN1160183A (en) * | 1995-03-09 | 1997-09-24 | 费罗马托姆公司 | U-tube heat exchanger, equipped with tube antivibration stabilizing system and hold-down system |
| CN1076462C (en) * | 1993-10-20 | 2001-12-19 | 法玛通公司 | Device for antivibrational blocking of tubes of a heat exchanger and use |
| US20120304466A1 (en) * | 2011-06-02 | 2012-12-06 | Westinghouse Electric Company Llc | Anti-vibration bar clamping tool |
| CN203026152U (en) * | 2012-12-13 | 2013-06-26 | 中国核动力研究设计院 | Anti-vibration strip structure for steam generator in pressurized water reactor nuclear power plant |
-
2012
- 2012-12-13 CN CN201210538916.3A patent/CN103871488A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5447191A (en) * | 1993-08-20 | 1995-09-05 | Framatome | Heat exchanger including means for holding antivibration bars interposed between the tubes of the bundle of the exchanger |
| CN1076462C (en) * | 1993-10-20 | 2001-12-19 | 法玛通公司 | Device for antivibrational blocking of tubes of a heat exchanger and use |
| CN1160183A (en) * | 1995-03-09 | 1997-09-24 | 费罗马托姆公司 | U-tube heat exchanger, equipped with tube antivibration stabilizing system and hold-down system |
| US20120304466A1 (en) * | 2011-06-02 | 2012-12-06 | Westinghouse Electric Company Llc | Anti-vibration bar clamping tool |
| CN203026152U (en) * | 2012-12-13 | 2013-06-26 | 中国核动力研究设计院 | Anti-vibration strip structure for steam generator in pressurized water reactor nuclear power plant |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107221357A (en) * | 2017-05-24 | 2017-09-29 | 四川行之智汇知识产权运营有限公司 | Heat exchanging chamber in integral vibration damping type reactor evaporator |
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Application publication date: 20140618 |