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Zirconium-niobium-iron alloys for nuclear power plant fuel cladding

A fuel cladding and iron-based alloy technology is applied in the field of zirconium alloy materials to achieve the effect of excellent corrosion resistance

Active Publication Date: 2018-08-03
SHANGHAI UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

We choose Zr-1Nb-015Fe as the master alloy and add S / Ge, S / Bi, Cu / Bi, Cu / Bi / Fe and Cu / Bi / Ge in combination. The effect on its microstructure and corrosion resistance has not been reported yet.

Method used

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  • Zirconium-niobium-iron alloys for nuclear power plant fuel cladding
  • Zirconium-niobium-iron alloys for nuclear power plant fuel cladding

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Embodiment 1

[0017] See Table 1, which shows the composition of five typical zirconium-niobium-iron alloys 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-mentioned ingredients, use a vacuum non-consumable electric arc furnace to melt into an ingot of about 65g, fill it with high-purity argon for protection, and turn each ingot repeatedly for 6 times to obtain an alloy with a uniform composition ingot;

[0021] (2) Heat the above-mentioned ingot to 700°C, hot-press with molds of different heights, each time the reduction is about 60%, and process it into a billet, the purpose is to break the coarse as-cast grain structure;

[0022] (3) After descaling and pickling, the billet is heated to 1030°C in a tube furnace, held for 40 minutes, and air-cooled; then the sample is heated to 700°C, and hot-rolled into a plate with a thickness of about 1.6 mm;...

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Abstract

The invention relates to a Zr-Nb-Fe alloy used for structural materials such as fuel claddings and spacer grid stripes in a pressurized water reactor nuclear power plant, belonging to the technical field of Zr alloy materials. The Zr alloy comprises the following chemical components in percentage by weight: 0.8%-1.2% of Nb, 0.1%-0.4% of Fe, 10 mu g / g-100 mu g / g of S, 0.01%-0.2% of Cu, 0.01%-0.3% of Bi, 0.01%-0.2% of Ge and the balance of Zr. Preferably, the alloy comprises the following elements in percentage by weight: 0.9%-1.1% of Nb, 0.1%-0.3% of Fe, 0.03%-0.07% of Cu, 0.04%-0.07% of Bi, 0.03%-0.07% of Ge and the balance of Zr. The Zr alloy has excellent corrosion-resistance in superheated steam of 400 DEG C and 10.3 MPa and deionized water of 360 DEG C and 18.6 MPa, and is obviously superior to a Zr-1Nb-0.15Fe alloy; and the machinability is good, so that the Zr-Nb-Fe alloy can be used as reactor core structural materials such as fuel element claddings and spacer grid stripes in the nuclear power plant pressurized water reactor.

Description

technical field [0001] The invention relates to a zirconium-niobium-iron series 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 prepared by adding a small amount of alloy elements on the basis of it has excellent nuclear properties, moderate mechanical properties and good corrosion resistance in high temperature and high pressure water and superheated steam, so it is As the cladding material of nuclear fuel elements, it is widely used in water-cooled reactor nuclear power plants, and is a very important structural material in pressurized water reactor nuclear power plants. In order to further increase the fuel consumption of nuclear fuel and reduce the cost of nuclear power, it is necessary to take measu...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22C16/00C22F1/18G21C3/07
CPCC22C16/00C22F1/186G21C3/07Y02E30/30
Inventor 姚美意吴晓彤胡洋段文荣王波阳张金龙周邦新
Owner SHANGHAI UNIV