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Zirconium/niobium/copper/bismuth alloy for fuel cladding of nuclear power plant

A technology for fuel cladding and nuclear power plants, which is applied in the field of zirconium alloy materials to achieve excellent corrosion resistance and improve corrosion resistance.

Inactive Publication Date: 2015-11-04
SHANGHAI UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Zr-1Nb is a commercial zirconium alloy, the effect of compound addition of different contents of Bi and Cu on its microstructure and corrosion resistance has not been reported

Method used

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  • Zirconium/niobium/copper/bismuth alloy for fuel cladding of nuclear power plant
  • Zirconium/niobium/copper/bismuth alloy for fuel cladding of nuclear power plant

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Embodiment 1

[0017] See Table 1, which shows the composition of five typical zirconium-niobium-copper-bismuth materials according to the present invention.

[0018]

[0019] The alloy materials with the composition in Table 1 were prepared according to the following steps:

[0020] (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;

[0021] (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;

[0022] (3) After removing the scale and pickling, the billet is subjected to β-phase homogenization treatment at 1030-1050 °C in vacuum for 0.5-1 h and then air-cooled; then it is hot-rolled at 700 °C. After hot-roll...

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Abstract

The invention relates to a zirconium / niobium / copper / bismuth alloy used as such structural materials as a fuel cladding of a pressurized water reactor nuclear power plant and a positioning grillwork strip, and belongs to the technical field of zirconium alloy materials. The zirconium alloy comprises the following chemical components in percentage by weight: 0.7-1.2% of Nb, 0.05-0.6% of Cu, 0.05-1.0% of Bi, and the balance of Zr. The preferential range of the alloy elements is as follows: 0.8-1.2% of Nb, 0.1-0.4% of Cu, and 0.1-0.4% of Bi. The zirconium alloy is excellent in corrosion resistance in superheated steam of 400 DEG C / 10.3 MPa and de-ionized water of 360 DEG C / 18.6 MPa, is obviously superior to a Zr-1Nb alloy, is excellent in machinability, and can be used as such core structural materials as the fuel element cladding and the positioning grillwork strip in a pressurized water reactor of the nuclear power plant.

Description

technical field [0001] The invention relates to a zirconium-niobium-copper-bismuth alloy used as structural materials such as fuel cladding and positioning grid strips of a pressurized water reactor nuclear power plant, and belongs to the technical field of zirconium alloy materials. Background technique [0002] The thermal neutron absorption cross section of zirconium is small, and the zirconium alloy made by adding a small amount of alloy elements has good high temperature water corrosion resistance, good comprehensive mechanical properties and high thermal conductivity, and is currently the only fuel element used in pressurized water reactors. The cladding material is the first safety barrier when the reactor is running. In order to reduce the cost of nuclear power, it is necessary to increase the burnup of nuclear fuel, which inevitably prolongs the refueling cycle of nuclear fuel assemblies. Fuel assemblies need to run for a longer time in the reactor core, thus putti...

Claims

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Application Information

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IPC IPC(8): C22C16/00G21C3/07
CPCY02E30/30
Inventor 姚美意张金龙孙风涛周邦新
Owner SHANGHAI UNIV
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