CN103868051B - PWR nuclear power plant steam generator march-past vibrationproof bar structure - Google Patents

PWR nuclear power plant steam generator march-past vibrationproof bar structure Download PDF

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Publication number
CN103868051B
CN103868051B CN201210538716.8A CN201210538716A CN103868051B CN 103868051 B CN103868051 B CN 103868051B CN 201210538716 A CN201210538716 A CN 201210538716A CN 103868051 B CN103868051 B CN 103868051B
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China
Prior art keywords
vibrationproof bar
series
vibrationproof
bar
steam generator
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CN201210538716.8A
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Chinese (zh)
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CN103868051A (en
Inventor
谈国伟
王园
李磊
汤臣杭
周永
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中国核动力研究设计院
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Priority to CN201210538716.8A priority Critical patent/CN103868051B/en
Publication of CN103868051A publication Critical patent/CN103868051A/en
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Publication of CN103868051B publication Critical patent/CN103868051B/en

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Abstract

The present invention relates to PWR nuclear power plant steam generator heat-transfer pipe bend loss supporting technology field, specifically disclose a kind of PWR nuclear power plant steam generator march-past vibrationproof bar structure.This march-past vibrationproof bar structure, be included in the some groups of vibrationproof bar assemblies that U-shaped heat-transfer pipe bend pipe pipeline section place installs, often organize vibrationproof bar assembly to be made up of some vibrationproof bars, and each group vibrationproof bar is divided into First Series vibrationproof bar and second series vibrationproof bar, wherein, First Series vibrationproof bar is arranged on sustained height h1, second series vibrationproof bar is arranged on sustained height h2, and h1 is higher than h2, the end tip of each vibrationproof bar is fixed with end cap, and the end cap of First Series vibrationproof bar is fixed on above retaining ring, the end cap of second series vibrationproof is fixed on below retaining ring.This march-past vibrationproof bar structure, various aspects of performance is better than existing two generations and adds unit vibrationproof bar assembly, can realize the supporting to steam generator U-shaped heat-transfer pipe bend pipe pipeline section, meanwhile, have larger circulation area, reduces flow resistance.

Description

PWR nuclear power plant steam generator march-past vibrationproof bar structure

Technical field

The invention belongs to PWR nuclear power plant steam generator heat-transfer pipe bend loss supporting technology field, be specifically related to a kind of PWR nuclear power plant steam generator march-past vibrationproof bar structure.

Background technology

Vertical, inverted-loop tube, natural circulation steam generator (hereinafter referred to as SG) are the main flow SG patterns that domestic nuclear power plant adopts.The vibrationproof bar assembly being positioned at heat-transfer pipe bend loss is vitals U-shaped pipe bend loss being provided to supporting, and the quality of its structural design is not only related to the fretting of pipe, stress corrosion, heat transfer conditions, also directly has influence on the height of SG circulating ratio.

In domestic two generations, add unit Application comparison vibrationproof bar assembly widely, above-mentioned institute summary point show not all roses, especially have to be hoisted in flow resistance performance.External Westinghouse Electric has designed the vibrationproof bar assembly of new structure, estimates to obtain good result in reduction flow resistance.

But what Westinghouse Electric's design adopted on vibrationproof bar end connecting is neat arrangement mode, is namely all positioned at the same side of retaining ring, so there is the narrow problem of free air space, be unfavorable for the reduction of parts flow resistance.

Summary of the invention

The object of the present invention is to provide a kind of PWR nuclear power plant steam generator march-past vibrationproof bar structure, the supporting to steam generator U-shaped heat-transfer pipe bend pipe pipeline section can be realized, meanwhile, there is larger circulation area, reduce flow resistance.

Technical scheme of the present invention is as follows: a kind of PWR nuclear power plant steam generator march-past vibrationproof bar structure, be included in the some groups of vibrationproof bar assemblies that steam generator U-shaped heat-transfer pipe bend pipe pipeline section place installs, often organize vibrationproof bar assembly to be made up of some vibrationproof bars, and each group vibrationproof bar is divided into First Series vibrationproof bar and second series vibrationproof bar, wherein, First Series vibrationproof bar is arranged on sustained height h1 relative to top support plate upper surface, second series vibrationproof bar is arranged on sustained height h2 relative to top support plate upper surface, and First Series vibrationproof bar height h1 is higher than second series vibrationproof bar height h2, the end tip of each vibrationproof bar in First Series vibrationproof bar and second series vibrationproof bar is fixedly connected with end cap, the end cap of First Series vibrationproof bar end is fixed on above retaining ring, and the end cap of second series vibrationproof bar end is fixed on the below of retaining ring.

Described retaining ring cross section is wedge structure, and the end cap of First Series vibrationproof bar end is fixedly welded on lozenges above retaining ring, and the end cap of second series vibrationproof bar end is fixedly welded on lozenges below retaining ring.

The cross section of described retaining ring is isosceles trapezoid, and the drift angle that this isosceles trapezoid two kidney-shaped becomes is 20 °, trapezoidal upper length of side 10mm, high 15mm;

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 PWR nuclear power plant steam generator march-past vibrationproof bar structure of the present invention, various aspects of performance is better than existing two generations and adds unit vibrationproof bar assembly, the supporting to steam generator U-shaped heat-transfer pipe bend pipe pipeline section can be realized, simultaneously, there is larger circulation area, reduce flow resistance.

Accompanying drawing explanation

Fig. 1 is a kind of PWR nuclear power plant steam generator march-past vibrationproof bar structural representation of the present invention;

Fig. 2 is A place partial enlarged drawing in Fig. 1;

Fig. 3 is march-past vibrationproof bar structure end enlarged drawing in Fig. 1;

In figure: 1, U-shaped heat-transfer pipe; 2, vibrationproof bar; 3, end cap; 4, retaining ring; 5, maintaining item.

Detailed description of the invention

Below in conjunction with drawings and the specific embodiments, the present invention is described in further detail.

As shown in Figures 1 to 3, a kind of PWR nuclear power plant steam generator march-past vibrationproof bar structure, be included in the some groups of vibrationproof bar assemblies that steam generator U-shaped heat-transfer pipe 1 bend pipe pipeline section place installs, often organize vibrationproof bar assembly to be made up of some vibrationproof bars 2, and each group vibrationproof bar is divided into First Series vibrationproof bar and second series vibrationproof bar, wherein, First Series vibrationproof bar is arranged on sustained height h1 relative to top support plate upper surface, second series vibrationproof bar is arranged on sustained height h2 relative to top support plate upper surface, and First Series vibrationproof bar height h1 is higher than second series vibrationproof bar height h2, the end tip of each vibrationproof bar 2 in First Series vibrationproof bar and second series vibrationproof bar is fixedly connected with by two pins the end cap 3 that nickel-base material makes, the end cap 3 of First Series vibrationproof bar end is fixedly welded on above the retaining ring 4 that nickel-base material makes, and the end cap 3 of second series vibrationproof bar end is fixedly welded on the below of retaining ring 4, wherein, retaining ring 4 cross section is wedge structure, be convenient to be welded and fixed with the end cap 3 of First Series vibrationproof bar and second series vibrationproof bar, such as, the cross section of retaining ring 4 is isosceles trapezoid, the drift angle that this isosceles trapezoid two kidney-shaped becomes is 20 °, trapezoidal upper length of side 10mm, high 15mm, 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. a PWR nuclear power plant steam generator march-past vibrationproof bar structure, be included in the some groups of vibrationproof bar assemblies that the U-shaped heat-transfer pipe of steam generator (1) bend pipe pipeline section place installs, it is characterized in that: often organize vibrationproof bar assembly and be made up of some vibrationproof bars (2), and each group vibrationproof bar is divided into First Series vibrationproof bar and second series vibrationproof bar, wherein, First Series vibrationproof bar is arranged on sustained height h1 relative to top support plate upper surface, second series vibrationproof bar is arranged on sustained height h2 relative to top support plate upper surface, and First Series vibrationproof bar height h1 is higher than second series vibrationproof bar height h2, the end tip of each vibrationproof bar (2) in First Series vibrationproof bar and second series vibrationproof bar is fixedly connected with end cap (3), the end cap (3) of First Series vibrationproof bar end is fixed on retaining ring (4) top, and the end cap (3) of second series vibrationproof bar end is fixed on the below of retaining ring (4).
2. PWR nuclear power plant steam generator march-past vibrationproof bar structure according to claim 1, it is characterized in that: described retaining ring (4) cross section is wedge structure, the end cap (3) of First Series vibrationproof bar end is fixedly welded on retaining ring (4) top lozenges, and the end cap (3) of second series vibrationproof bar end is fixedly welded on retaining ring (4) below lozenges.
3. PWR nuclear power plant steam generator march-past vibrationproof bar structure according to claim 1, it is characterized in that: the cross section of described retaining ring (4) is isosceles trapezoid, the drift angle that this isosceles trapezoid two kidney-shaped becomes is 20 °, trapezoidal upper length of side 10mm, high 15mm.
4. PWR nuclear power plant steam generator march-past vibrationproof bar structure according to claim 1, it is characterized in that: between the outer U-shaped heat-transfer pipe (1) of described steam generator, 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. the march-past vibrationproof bar structure of the PWR nuclear power plant steam generator according to any one of claims 1 to 3, 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. PWR nuclear power plant steam generator march-past vibrationproof bar structure according to claim 4, is characterized in that: described maintaining item (5) is made up of nickel-base material.
7. PWR nuclear power plant steam generator march-past vibrationproof bar structure 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.
CN201210538716.8A 2012-12-13 2012-12-13 PWR nuclear power plant steam generator march-past vibrationproof bar structure CN103868051B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201210538716.8A CN103868051B (en) 2012-12-13 2012-12-13 PWR nuclear power plant steam generator march-past vibrationproof bar structure

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Application Number Priority Date Filing Date Title
CN201210538716.8A CN103868051B (en) 2012-12-13 2012-12-13 PWR nuclear power plant steam generator march-past vibrationproof bar structure

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CN103868051A CN103868051A (en) 2014-06-18
CN103868051B true CN103868051B (en) 2015-08-26

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Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107221357B (en) * 2017-05-24 2019-04-09 安徽科创智慧知识产权服务有限公司 Heat exchanging chamber in integral vibration damping type reactor evaporator

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4230527A (en) * 1977-04-29 1980-10-28 Alexander Cella Steam generator for use in nuclear power plants
CN85108329A (en) * 1984-11-13 1986-10-15 西屋电气公司 The anti-vibration bars of nuclear steam generators
EP0214812A2 (en) * 1985-09-06 1987-03-18 Westinghouse Electric Corporation Antivibration bar installation apparatus
US4665866A (en) * 1985-09-04 1987-05-19 Westinghouse Electric Corp. Grid-type flow distribution baffle
CN1045481A (en) * 1989-03-09 1990-09-19 法玛通公司 Bundle of steam generator stabilising arrangement with vibration resistance bar
CN102794608A (en) * 2012-08-20 2012-11-28 丹阳市龙鑫合金有限公司 Anti-vibration strip component of steam generator of AP1000 nuclear power unit
CN203024132U (en) * 2012-12-13 2013-06-26 中国核动力研究设计院 March-type anti-vibration strip structure for pressurized water reactor nuclear power plant steam generator

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4230527A (en) * 1977-04-29 1980-10-28 Alexander Cella Steam generator for use in nuclear power plants
CN85108329A (en) * 1984-11-13 1986-10-15 西屋电气公司 The anti-vibration bars of nuclear steam generators
US4665866A (en) * 1985-09-04 1987-05-19 Westinghouse Electric Corp. Grid-type flow distribution baffle
EP0214812A2 (en) * 1985-09-06 1987-03-18 Westinghouse Electric Corporation Antivibration bar installation apparatus
CN1045481A (en) * 1989-03-09 1990-09-19 法玛通公司 Bundle of steam generator stabilising arrangement with vibration resistance bar
CN102794608A (en) * 2012-08-20 2012-11-28 丹阳市龙鑫合金有限公司 Anti-vibration strip component of steam generator of AP1000 nuclear power unit
CN203024132U (en) * 2012-12-13 2013-06-26 中国核动力研究设计院 March-type anti-vibration strip structure for pressurized water reactor nuclear power plant steam generator

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