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A kind of brazing connection technology of zirconium alloy and stainless steel for nuclear reactor

A nuclear reactor and zirconium alloy technology, applied in welding equipment, metal processing equipment, manufacturing tools, etc., can solve problems such as low toughness, increased corrosion, and greater harm to human body, and achieve high toughness and good corrosion resistance in high temperature water.

Active Publication Date: 2016-07-06
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] The invention provides a brazing connection process of zirconium alloy for nuclear reactor and stainless steel, which solves the problem of the dissolution of the brazing filler metal on the base material of the base material in the brazing connection process of zirconium alloy for reactor and stainless steel in the prior art, and with the brazing time Elongation, intensified corrosion, poor high temperature water corrosion resistance of the joints, generally low toughness, and the use of beryllium-containing solder is more harmful to the human body, and the phenomenon of phase change grain growth of the zirconium alloy base material will occur, resulting in structural parts The technical problem of performance degradation has realized that the solder will not dissolve the base metal, the joint has good corrosion resistance in high temperature water, and has high toughness, and the use of solder containing beryllium is less harmful to the human body, and zirconium will not appear Alloy base material phase transformation grain growth phenomenon, the technical effect of better performance of structural parts

Method used

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  • A kind of brazing connection technology of zirconium alloy and stainless steel for nuclear reactor
  • A kind of brazing connection technology of zirconium alloy and stainless steel for nuclear reactor
  • A kind of brazing connection technology of zirconium alloy and stainless steel for nuclear reactor

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Embodiment 1

[0041] In Embodiment 1, a brazing connection process between zirconium alloy and stainless steel for nuclear reactor is provided, please refer to Figure 1-Figure 5 , the process includes:

[0042] S10, carry out structural design of zirconium alloy unit and stainless steel unit;

[0043] S20, performing surface modification treatment on the zirconium alloy unit;

[0044] S30, cleaning and assembling the zirconium alloy unit and the stainless steel unit;

[0045] S40, performing low-temperature pretreatment on the assembled components;

[0046] S50, brazing the components after the low-temperature pretreatment.

[0047] Wherein, in the embodiment of the present application, the process steps also include after brazing:

[0048] Conduct performance testing of the brazed components;

[0049] The components after performance testing are processed into finished products.

[0050] Wherein, in the embodiment of the present application, the base material for brazing is zirconiu...

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Abstract

The invention discloses a brazed connection technology of zirconium alloy and stainless steel for a nuclear reactor. The technology comprises the steps that structure designing of a zirconium alloy unit and a stainless steel unit is carried out first, then zirconium alloy unit surface modified processing is carried out, then the zirconium alloy unit and the stainless steel unit are subjected to washing and assembling, then an assembled part is subjected to low-temperature preprocessing, and finally the part obtained after low-temperature preprocessing is subjected to brazing. The fact that brazing filler metal cannot corrode matrix materials is achieved, the high-temperature-water-corrosion resistance of a connector is good, tenacity is high, brazing filler metal with beryllium is not used, damage to a human body is low, the phenomenon that zirconium alloy base metal phase-change crystalline grains grow is avoided, and a structure piece is good in performance.

Description

technical field [0001] The invention relates to the technical field of nuclear power equipment welding, in particular to a brazing connection process of zirconium alloy and stainless steel for nuclear reactors. Background technique [0002] The zirconium alloy and stainless steel transition joint is a structural part for connecting the zirconium alloy fuel cladding tube and the stainless steel electric heating element casing in the reactor fuel cladding experimental device. The experimental device simulates the operating state of the nuclear reactor, and tests the various states of the fuel cladding material of the fuel element under normal operation and accident conditions. The structural part of the transition joint is a tubular structure with a length of 100mm, an outer diameter of ¢10mm~¢12mm, and an inner diameter of ¢6mm. It is welded by zirconium alloy and stainless steel (please refer to the attached figure 1 ). The welding performance of zirconium alloy and stainl...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B23K1/20
CPCB23K1/20B23K1/206
Inventor 杨军王飞朱金霞薛敬凯罗绪珍王建马勇哲刘晓荣
Owner NUCLEAR POWER INSTITUTE OF CHINA
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