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Preparation technology of FeCrAl pipe material for nuclear fuel element

A preparation process and nuclear fuel technology, which is applied in the field of preparation process of FeCrAl pipes for nuclear fuel elements, can solve problems such as changes in mechanical properties, increase in strength, and decrease in ductility, and achieve the effects of saving man-hours, good benefits, and smooth inner and outer surfaces

Inactive Publication Date: 2018-06-15
INST OF METAL RESEARCH - CHINESE ACAD OF SCI +3
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

In nuclear reactors, the working conditions of the zirconium alloy cladding tube are very harsh, not only need to withstand high temperature, high pressure and strong neutron irradiation, but also require high boron water corrosion resistance, stress corrosion, etc., with time, the mechanical properties Changes occur, strength increases, ductility decreases, and becomes brittle, so it needs to be replaced every 12 months, which is a high-consumable product

Method used

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  • Preparation technology of FeCrAl pipe material for nuclear fuel element
  • Preparation technology of FeCrAl pipe material for nuclear fuel element
  • Preparation technology of FeCrAl pipe material for nuclear fuel element

Examples

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Effect test

Embodiment 1

[0025] Vacuum induction melting FeCrAl alloy ingot, its composition ratio is: Cr 13%; Al 5%; Y 0.05%; Mo1%; Si 0.005%; C 0.05%; N≤500ppm; O≤1000ppm; P≤500ppm; S≤500ppm; the balance is Fe, forged into a Φ28mm round bar at 1000°C, with a deformation of 60%, and then subjected to solution heat treatment at 800°C for 30 minutes, and processed into a Φ25mm×5mm tube blank by machining and drilling. The pipe is cold-rolled and annealed repeatedly 10 times, and rolled into a Φ9.5mm×0.3mm pipe. Finished Organization See image 3 , the rolling process parameters are shown in Table 1.

[0026] Table 1 embodiment 1 rolling process parameter

[0027]

Embodiment 2

[0029] Vacuum induction melting FeCrAl alloy ingot, its composition ratio is Cr 8%; Al 6%; Y 0.09%; Mo5%; Si 0.01%; C 0.05%; N≤500ppm; O≤1000ppm; P≤500ppm; S ≤500ppm; the balance is Fe, forged into a Φ28mm round bar at 1000℃, deformed by 47%, and then subjected to solution heat treatment at 900℃×20 minutes, and processed into a Φ25mm×5mm tube blank by machining and drilling. Repeated cold rolling and annealing for 10 times, rolled into Φ10mm×0.2mm pipe, the structure is shown in Figure 4 , the rolling process parameters are shown in Table 2.

[0030] Table 2 embodiment 2 rolling process parameters

[0031]

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Abstract

The invention relates to a preparation method of a FeCrAl pipe material for a nuclear fuel element, and belongs to the technical field of nuclear power pipe material preparation. The preparation method comprises the technological processes that alloy ingot is obtained through smelting, the alloy ingot is forged into bars and then machined to obtain a pipe blank, and the alloy pipe material is prepared by adopting a finish rolling technology. The preparation method is characterized in that cold rolling total deformation is controlled within the range of 10% to 50%, the cold rolling feeding amount is controlled within the range of 0.5 to 2, the rolling pass is controlled within the range of 3 to 15, the rotation speed is controlled within the range of 15 r / min to 60 r / min, the annealing temperature ranges from 700 DEG C to 1,100 DEG C, and heat preservation is conducted for 20-60 min. The method has the characteristics of being simple in technology, high in production flexibility and lowin cost.

Description

technical field [0001] The invention relates to a preparation process of FeCrAl alloy pipe material for nuclear fuel. Background technique [0002] In nuclear power design, the first line of defense for nuclear safety is the cladding material of nuclear fuel → cladding tube. Its function is to coat the fuel core to prevent the release of fission products into the coolant. It cannot be damaged to cause radioactive spillage, and is currently made of zirconium alloy precision cold-rolled tubes. In nuclear reactors, the working conditions of the zirconium alloy cladding tube are very harsh, not only need to withstand high temperature, high pressure and strong neutron irradiation, but also require high boron water corrosion resistance, stress corrosion, etc., with time, the mechanical properties Changes occur, the strength increases, the ductility decreases, and it becomes brittle, so it needs to be replaced every 12 months, which is a high-consumable product. The FeCrAl alloy ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C21D8/10C22C38/22C22C38/06C22C38/02B21C37/06
CPCC21D8/105B21C37/06C22C38/004C22C38/005C22C38/02C22C38/06C22C38/22
Inventor 张伟红杨英孙文儒祁峰贾丹李胜超蔡尧翟剑晗李锐
Owner INST OF METAL RESEARCH - CHINESE ACAD OF SCI
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