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A kind of zirconium alloy and preparation method thereof

A technology of zirconium alloy and master alloy, applied in the field of zirconium alloy and its preparation

Inactive Publication Date: 2016-03-23
CHONGQING UNIV
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0006] However, with the development of nuclear fuel assemblies in the direction of long life and high burnup, zirconium alloys as reactor structural materials must have better comprehensive properties such as corrosion resistance, creep resistance, and radiation growth resistance, while Zr-2 and Zr- The fuel consumption design value that 4 alloys can meet is usually 33GWd / tU, which is no longer satisfactory. Therefore, it is necessary to study new zirconium alloys with higher strength and plasticity for reactor structural materials, and the current research trends of new zirconium alloys are all In order to adjust the alloy composition content and add other alloy elements on the basis of Zr-Nb series and Zr-Sn-Nb series alloys, or both at the same time to achieve the purpose of improving the overall performance of the alloy

Method used

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  • A kind of zirconium alloy and preparation method thereof
  • A kind of zirconium alloy and preparation method thereof
  • A kind of zirconium alloy and preparation method thereof

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preparation example Construction

[0047] The present invention also provides a preparation method of the above-mentioned zirconium alloy, which includes the following steps: a) mixing Bi, Mo, Cr, Fe and Zr, and melting to obtain a zirconium alloy; wherein the content of Bi is 0.05-0.8wt%, and the content of Mo The content of Cr is 0.05~1.0wt%, the content of Cr is 0.4~1.2wt%, the content of Fe is 0.1~0.5wt%, and the balance is Zr.

[0048] Wherein, according to the present invention, the Bi, Mo, Cr, Fe and Zr elements are the same as those mentioned above, and will not be repeated here.

[0049] Step a) described in the present invention is specifically: a1) mixing Zr and Bi, melting, to obtain Zr-Bi master alloy; a2) mixing said Zr-Bi master alloy, Zr, Fe, Cr and Mo, melting, A zirconium alloy is obtained.

[0050] The smelting method in the step a1) can be a method well-known to those skilled in the art, and there is no special limitation, and the conditions of the smelting can also be a method well-known t...

Embodiment 1

[0056] 1.1 Mix and melt 100g Zr and 110gBi to obtain a Zr-Bi master alloy, and through chemical analysis, the specific content of Bi element is 50wt%.

[0057] 1.2 Pulverize 0.2g of the Zr-Bi master alloy obtained in 1.1 and add it to the mixture of 48.9gZr, 0.2gFe, 0.5gCr and 0.2gMo, and then use a non-consumable vacuum electric arc furnace at a vacuum degree of 5×10 -3 Pa, 0.5atm under the protection of argon smelting 5 times to obtain a zirconium alloy, wherein the content of Bi is 0.2wt%, the content of Mo is 0.4wt%, the content of Cr is 1.0wt%, and the content of Fe is 0.4wt%. , The content of Zr is 98wt%.

[0058] The mechanical properties of the zirconium alloy obtained in 1.2 were tested to obtain its tensile strength, yield strength and elongation. As shown in Table 1, the zirconium alloy was hot-rolled and annealed, and then the mechanical properties were tested at room temperature to obtain Its tensile stress-strain curve, such as figure 1 , where A is the stress-...

Embodiment 2

[0060] 2.1 Mix and melt 100g Zr and 110gBi to obtain a Zr-Bi master alloy, and through chemical analysis, the specific content of Bi element is 50wt%.

[0061] 2.2 Pulverize 0.4g of the Zr-Bi master alloy obtained in 2.1 and add it to the mixture of 48.7gZr, 0.2gFe, 0.5gCr and 0.2gMo, and then use a non-consumable vacuum electric arc furnace at a vacuum degree of 5×10 -3 Pa, 0.5atm under the protection of argon smelting 5 times to obtain a zirconium alloy, wherein the content of Bi is 0.4wt%, the content of Mo is 0.4wt%, the content of Cr is 1.0wt%, and the content of Fe is 0.4wt%. , The content of Zr is 97.8wt%.

[0062] The zirconium alloy obtained in 2.2 is hot-rolled and annealed, and then the mechanical properties are tested at room temperature to obtain its tensile stress-strain curve, such as figure 2 , where A is the stress-strain curve of tensile sample 1, and B is the stress-strain curve of tensile sample 2.

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Abstract

The invention provides zirconium alloy and a preparation method thereof. The zirconium alloy comprises, 0.05-0.8 wt% of Bi, 0.05-1.0 wt% of Mo, 0.4-1.2 wt% of Cr, 0.1-0.5 wt% of Fe and the balance Zr. Compared with conventional zirconium alloy, Mo and Bi are both added on the basis of Zr-Fe-Cr alloy. Firstly, Fe and Cr elements form a fine dispersively-distributed Zr(FeCr)2 precipitated phase which is capable of improving the strength of Zr alloy; also, by adding proper proportions of Fe and Cr elements, the corrosion resistant performance of zirconium alloy is improved; by adding a proper amount of Mo element into the alloy, a fine dispersive strengthening phase is obtained, and thus the high-temperature strength and the creep resistance of zirconium alloy are improved; and addition of Bi element further helps to improve the stretching strength of the alloy, and helps to balance the brittleness brought by Mo element and improve the plasticity of zirconium alloy.

Description

technical field [0001] The invention belongs to the technical field of alloy materials, in particular to a zirconium alloy and a preparation method thereof. Background technique [0002] Zirconium alloys have low neutron absorption cross section, good thermal conductivity, good high temperature water corrosion resistance and radiation growth resistance, so zirconium alloys are widely used as cladding materials for fuel rods and nuclear reactor cores in water-cooled nuclear reactors structural elements. [0003] With the development of nuclear power reactor technology in the direction of increasing fuel consumption, reducing dye cycle costs, increasing reactor efficiency, and improving safety and reliability, the corrosion resistance, hydrogen absorption performance, and Higher requirements are put forward for mechanical properties and radiation dimensional stability. Fuel elements will experience creep and fatigue under service conditions (irradiation, high temperature, hi...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22C16/00C22C1/03
Inventor 栾佰峰杨柳青刘庆龙冲生
Owner CHONGQING UNIV
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