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U-shaped heat transfer tube single-tube dynamic characteristic test device for vertical steam generator of nuclear power plant

A technology of steam generator and dynamic characteristics, applied in nuclear power generation, cooling devices, nuclear engineering, etc., can solve problems such as heat transfer tube damage, thermal efficiency reduction, accident shutdown, etc.

Pending Publication Date: 2019-07-23
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] Damage to heat transfer tubes caused by water flow vibration will reduce thermal efficiency and cause radioactive leakage, and in severe cases will cause accidental shutdown

Method used

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  • U-shaped heat transfer tube single-tube dynamic characteristic test device for vertical steam generator of nuclear power plant
  • U-shaped heat transfer tube single-tube dynamic characteristic test device for vertical steam generator of nuclear power plant
  • U-shaped heat transfer tube single-tube dynamic characteristic test device for vertical steam generator of nuclear power plant

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Experimental program
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Embodiment Construction

[0023] In order to make the above objects, features and advantages of the present invention more comprehensible, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0024] An embodiment of the present invention provides a U-shaped heat transfer tube single-tube dynamic characteristic test device for a vertical steam generator in a nuclear power plant. Heat pipe, the detailed structure of the test piece is as follows figure 1 shown.

[0025] For the single-tube test piece, the spans of the first and last spans were kept consistent with the actual size, and the remaining 8 spans were reduced to 3 spans. The distance of the first span of the straight pipe section is 537mm, the distance of the middle three spans is 933mm×3, and the distance of the last span is 932mm.

[0026] Except for the shortening of the straight pipe section, the material, shape and size of the heat transfer tube are consi...

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Abstract

The invention provides a U-shaped heat transfer tube single-tube dynamic characteristic test device for a vertical steam generator of a nuclear power plant. The device includes a heat transfer tube, bottom supports, middle supports, bases and loading devices. The two ends of the heat transfer tube are fixed by the bottom supports. The part between the two ends of the heat transfer tube bundle is supported by the middle supports. The heat transfer tube bundle has two straight tube sections and an arc section. The two straight tube sections are connected to the two ends of the arc section. The arc section is loaded by the loading device. The heat transfer tube adopts a heat transfer tube with a maximum bending radius. The U-shaped heat transfer tube single-tube dynamic characteristic test device for a vertical steam generator of a nuclear power plant provided by the invention can complete a single-tube dynamic characteristic test, thereby obtaining factors affecting dynamic characteristics of a single tube of the heat transfer tube.

Description

technical field [0001] The invention relates to the design field of steam generators and heat exchangers, in particular to a dynamic characteristic test device for a U-shaped heat transfer tube single tube of a vertical steam generator in a nuclear power plant. Background technique [0002] The steam generator is the main device for removing the heat generated by the reactor core and is part of the pressure boundary of the reactor coolant system. The steam generator converts heat from the reactor coolant system into steam, which is fed to the turbogenerator to generate electricity. The steam generator is mainly composed of lower head, tube plate, secondary side shell, heat transfer tube bundle and steam-water separation device. Reliability requirements are high. [0003] Damage to heat transfer tubes caused by water flow vibration will reduce thermal efficiency and cause radioactive leakage, and in severe cases will cause accidental shutdown. Therefore, analyzing the vibr...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00G21C15/02
CPCG21C17/001G21C15/02Y02E30/30
Inventor 王赤虎陈清琦谢永诚张锴林绍萱祖洪彪邓晶晶张可丰梁星筠周全
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD