Germanium-containing Zr-Sn-Nb alloy for fuel cladding of nuclear power station

A technology for fuel cladding and nuclear power plants, applied in the field of zirconium-tin-niobium alloys, which can solve problems such as the inability to judge the corrosion resistance of new zirconium alloys, and achieve the effects of good processing performance, improved corrosion resistance, and excellent corrosion resistance

Active Publication Date: 2012-07-25
SHANGHAI UNIV +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

When studying the corrosion behavior of new zirconium alloys abroad, it is also found that due to the change of alloy composition, the corrosion test in superheated steam at 400 °C in the autoclave outside the reactor can no long

Method used

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  • Germanium-containing Zr-Sn-Nb alloy for fuel cladding of nuclear power station
  • Germanium-containing Zr-Sn-Nb alloy for fuel cladding of nuclear power station
  • Germanium-containing Zr-Sn-Nb alloy for fuel cladding of nuclear power station

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Experimental program
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Effect test

Embodiment 1

[0021] See Table 1, which shows the composition of three typical germanium-containing zirconium-tin-niobium alloy materials according to the present invention.

[0022] Table 1 Composition of germanium-zirconium-tin-niobium alloys 1 to 3 and comparative examples

[0023]

[0024] The alloy materials with the composition in Table 1 were prepared according to the following steps:

[0025] (1) According to the above formula and ingredients, use a vacuum non-consumable electric arc furnace to melt into an alloy ingot with a weight of about 65g, fill it with high-purity argon for protection during melting, and turn the alloy over and smelt it 6 times to make an alloy ingot with a uniform composition;

[0026] (2) The above-mentioned alloy ingot is hot-pressed at 700°C for several times, and processed into a billet, the purpose is to break the coarse as-cast grain structure;

[0027] (3) After the billet has been descaled and pickled, it is subjected to β-phase homogeni...

Embodiment 2

[0031]See Table 2, which shows the composition of three typical germanium-containing zirconium-tin-niobium alloy materials according to the present invention.

[0032] Table 2 Composition of germanium-zirconium-tin-niobium alloys 4 to 6 and comparative examples

[0033]

[0034] The alloy materials with the composition in Table 2 are prepared according to the following steps:

[0035] (1) According to the above formula and ingredients, use a vacuum non-consumable electric arc furnace to melt into an alloy ingot with a weight of about 65g, fill it with high-purity argon for protection during melting, and turn the alloy over and smelt it 6 times to make an alloy ingot with a uniform composition;

[0036] (2) The above-mentioned alloy ingot is hot-pressed at 700°C for several times, and processed into a billet, the purpose is to break the coarse as-cast grain structure;

[0037] (3) After the billet has been descaled and pickled, it is subjected to β-phase homogeniza...

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Abstract

The invention relates to a germanium-containing Zr-Sn-Nb alloy capable of being used as structural materials such as fuel cladding of a light water reactor nuclear power station, stripes of a location grid and the like, belonging to the technical field of zirconium alloy materials. The zirconium alloy comprises the following chemical components in percentage by weight: 0.3-1.5% of Sn, 0.1-1.2% of Nb, 0.03-0.4% of Fe, 0.02-0.3% of Cr, 0.01-0.8% of Ge and the balance of Zr, preferably 0.5-1.0% of Sn, 0.2-1.0% of Nb, 0.01-0.35% of Fe, 0.03-0.2% of Cr and 0.05-0.5% of Ge. The zirconium alloy can show excellent corrosion-resistant property in 360 DEG C/18.6MPa/0.01M LiOH aqueous solution, which is obviously better than Zr-4 alloy, is good in processability, and can be used as reactor core structural materials such as fuel element cladding of a pressurized water reactor of the nuclear power station, stripes of the location grid and the like.

Description

technical field [0001] The invention relates to a germanium-containing zirconium-tin-niobium alloy that can be used as structural materials such as light water reactor nuclear power plant fuel cladding and positioning grid strips, and belongs to the technical field of zirconium alloy materials. Background technique [0002] Zirconium has excellent nuclear properties, its thermal neutron absorption cross section is only 0.18 target, and it has good compatibility with uranium oxide, especially has good mechanical properties and high temperature water corrosion resistance, so zirconium alloys are widely used in water-cooled nuclear reactors Used as cladding material for fuel rods and structural material in fuel assemblies. In order to improve the economy of nuclear power, reduce the cycle cost of nuclear fuel, deepen the burnup of nuclear fuel, and improve the safety and reliability of nuclear power plants, it is necessary to improve the properties of zirconium alloys, includin...

Claims

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Application Information

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IPC IPC(8): C22C16/00G21C3/07
CPCY02E30/40Y02E30/30
Inventor 姚美意周邦新张金龙谢兴飞
Owner SHANGHAI UNIV
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