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High temperature overheated steam corrosion resistant zirconium alloy material

A technology of superheated steam and zirconium alloy, which is applied in the field of zirconium-based alloy materials

Active Publication Date: 2011-06-22
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0003] Conventional zirconium alloys (Zr-4, Zr-2.5Nb, M5, N18, N36, ZIRLO, E635, etc.) cannot meet the corrosion resistance requirements of high-temperature and high-pressure water at 400°C to 500°C, so it is necessary to research and develop high-temperature zirconium alloys

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  • High temperature overheated steam corrosion resistant zirconium alloy material
  • High temperature overheated steam corrosion resistant zirconium alloy material
  • High temperature overheated steam corrosion resistant zirconium alloy material

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Embodiment Construction

[0011] A zirconium alloy material resistant to corrosion by high-temperature superheated water vapor provided by the present invention will be further described in detail below in conjunction with examples.

[0012] A zirconium alloy material resistant to high-temperature superheated steam corrosion, which comprises the following components: 0.1-1.8% by weight of Fe, 0.1-1.8% by weight of Cr, C content less than 150 μg / g, N content less than Or equal to 50μg / g, the content of other impurities meets the current standard of zirconium alloys for nuclear use, and the balance is Zr.

[0013] The preferred weight percentage content range of the components of a zirconium alloy material Zr-Fe-Cr zirconium alloy resistant to high temperature superheated steam corrosion provided by the present invention is as shown in the following table 1:

[0014] Table 1 Zr-Fe-Cr zirconium alloy composition preferred weight percent content range

[0015]

[0016] The composition of a zirconium al...

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Abstract

The invention belongs to a zirconium-based alloy material and particularly discloses a high temperature overheated steam corrosion resistant zirconium alloy material, which comprises the following components: 0.1 to 1.8 weight percent of Fe, 0.1 to 1.8 weight percent of Cr, less than 150mug / g of C, less than or equal to 50mug / g of N, and the balance of Zr. The zirconium alloy material of the invention has much higher corrosion resistance in high temperature overheated steam at 500 DEG C and 10.3MPa compared with those of conventional zirconium alloys (for example, in a 360-hour corrosion test, the increased weight of the zirconium alloy of the invention is 75 to 80mg / dm<2>; while the increased weight of an N18 zirconium alloy is 230mg / dm<2>; and the increase weight of a Zr-4 zirconium alloy in a 50-hour corrosion test is 3,700mg / dm<2>.).

Description

technical field [0001] The invention belongs to zirconium-based alloy materials, in particular to a zirconium alloy material resistant to corrosion by high-temperature superheated water vapor. Background technique [0002] The general trend of reactor development is to increase fuel burnup to reduce fuel cycle costs, increase operating temperature to increase thermal efficiency and improve safety and reliability. higher requirements. The higher the operating temperature of the coolant in the reactor, the higher the thermal efficiency of nuclear power drive and power generation. If the operating temperature of the current water-cooled reactor is increased from about 300°C to 400-500°C, or even to the supercritical water temperature, the nuclear power Thermal efficiency can be improved a lot. However, the higher the operating temperature, the higher the performance of the cladding material and other core structural materials are required. [0003] Conventional zirconium all...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22C16/00G21C3/07
CPCY02E30/40Y02E30/30
Inventor 应诗浩王均王晓敏熊计范洪远苗志谭军
Owner NUCLEAR POWER INSTITUTE OF CHINA