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Novel supporting device for steam generator heat exchange tubes of pressurized water reactor nuclear power plant

A technology of a steam generator and a supporting device, which is applied in the field of a heat exchange tube supporting device for a steam generator of a new pressurized water reactor nuclear power plant, can solve problems such as affecting the heat transfer efficiency, so as to improve the heat transfer efficiency, reduce the local resistance coefficient, reduce the The effect of little resistance

Active Publication Date: 2014-06-18
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The design of the B-type SG support plate may cause the secondary side fluid of the steam generator to short-circuit through the large rectangular holes on the support plate, which will affect the heat transfer efficiency.

Method used

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  • Novel supporting device for steam generator heat exchange tubes of pressurized water reactor nuclear power plant
  • Novel supporting device for steam generator heat exchange tubes of pressurized water reactor nuclear power plant
  • Novel supporting device for steam generator heat exchange tubes of pressurized water reactor nuclear power plant

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Embodiment Construction

[0018] The present invention will be described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0019] Such as Figure 1~4 As shown, a new pressurized water reactor nuclear power plant steam generator heat exchange tube support device includes a heat exchange tube support plate 6 installed in the heat exchange tube bundle sleeve 2 in the steam generator 1, wherein the heat exchange tube support plate 6 installed in the steam generator The U-shaped heat exchange tubes 5 in the heat exchange tube bundle sleeve 2 of 1 are supported and fixed by several heat exchange tube support plates 6 parallel to each other, and the U-shaped heat exchange tube 5 located in the center of the heat exchange tube bundle sleeve 2 has the smallest bending radius The tube lane area 4 is formed in the heat exchange tube bundle sleeve 2, and the tube bundle area 3 is formed on both sides of the tube lane area 4; The tube wall forms a flow channel with a plum bl...

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Abstract

The invention relates to the technical field of steam generator heat exchangers and particularly discloses a novel supporting device for steam generator heat exchange tubes of a pressurized water reactor nuclear power plant. A U-shaped heat exchange tube mounted in a heat exchange tube bundle sleeve in the supporting device is supported and fixed through a plurality of parallel heat exchange tube supporting plates, a tube lane area is formed by the U-shaped heat exchange tube with the smallest bent radius, tube bundle area are formed in the two sides, and the supporting plates and the wall of the U-shaped heat exchange tube form flow channels with plum blossom petal holes in the section. Supporting boss edges for supporting the heat exchange tube supporting plates are distributed on the heat exchange tube supporting plates. The ratio of the sectional area of the heat exchange tube supporting plate channels to the sectional area of two heat exchange tube supporting plate rising channels in the supporting device is large, so that the local resistance factor of the heat exchange tube supporting plates is reduced, and resistance through the heat exchange tube supporting plates is reduced; meanwhile, due to retaining plates mounted on the heat exchange tube supporting plates, the fluid can be forced to flow into the tube bundle area to be participated in secondary side heat exchange of the steam generator, and accordingly, the steam generator heat transmission efficiency is improved.

Description

technical field [0001] The invention belongs to the technical field of steam generator heat exchangers, and in particular relates to a novel pressurized water reactor nuclear power plant steam generator heat exchange tube support device. Background technique [0002] In a typical vertical natural circulation steam generator (SG for short) of a pressurized water reactor nuclear power plant, several heat exchange tube support plates are arranged along the straight tube section of the tube bundle. The heat exchange tube support plate (hereinafter referred to as TSP) plays the role of supporting and fixing the heat transfer tube on the one hand, so as to prevent the tube from vibrating under the action of fluid flow. On the other hand, TSP provides channels for the flow of working fluid (steam, water mixture) on the secondary side of SG. [0003] The typical TSP structure of SG includes plum blossom orifice plate type, grid type and other forms. [0004] The TSP of a steam gen...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): F22B37/20G21D1/02
CPCY02E30/40Y02E30/00
Inventor 何戈宁张富源何劲松张冀辉
Owner NUCLEAR POWER INSTITUTE OF CHINA
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