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Zirconium-based alloy used in high-temperature environment of nuclear reactor

A high-temperature environment, zirconium-based alloy technology, applied in the field of zirconium alloy materials, can solve problems such as inability to meet performance requirements, and achieve excellent radiation creep resistance, improved mechanical properties, and radiation creep resistance.

Pending Publication Date: 2017-07-07
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Abstract
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  • Claims
  • Application Information

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Problems solved by technology

Although Zr-2 and Zr-4 alloys are used successfully, they cannot meet the performance requirements under high burnup
For example, when the fuel consumption of Japanese pressurized water reactor components is increased from 39000MWd / tU to 48000MWd / tU, the cladding tube is changed from Zr-4 alloy to low-tin Zr-4 alloy, but the latter cannot meet the further increase of fuel consumption to 55000MWd / tU Requirements, for which a new alloy NDA has been developed

Method used

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  • Zirconium-based alloy used in high-temperature environment of nuclear reactor
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  • Zirconium-based alloy used in high-temperature environment of nuclear reactor

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Embodiment Construction

[0028] In order to make the above objects, features and advantages of the present invention more comprehensible, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0029] Zirconium-based alloys used in the high-temperature environment of nuclear reactors, calculated by weight percentage, include: Sn: 0.36-0.69%; Nb: 0.20-0.49%; Fe: 0.21-0.40%; O: 0.10-0.20%; 0.09% Cu or composite addition of 0.01-0.09% Cu and 0.01-0.20% V; the balance is at least 98% zirconium containing impurities.

[0030] The compositions of the two examples and the comparative ZIRLO alloy are shown in Table 1.

[0031] Table 1

[0032]

[0033] The remaining impurity content is in line with the current standard of zirconium alloys for nuclear use, and the C and N impurity elements that are harmful to corrosion performance have been strictly controlled. The C content is less than 120μg / g, and the N content is less tha...

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Abstract

The invention provides a zirconium-based alloy used in high-temperature environment of a nuclear reactor. Calculated by weight percentage, the zirconium-based alloy comprises 0.36-0.69% of Sn, 0.20-0.49% of Nb, 0.21-0.40% of Fe, 0.10-0.20% of O, 0.01-0.09% of individually added Cu or 0.01-0.09% of compositely added Cu and 0.01-0.20 of compositely added V, and the balance of at least 98% of zirconium including impurities. The zirconium-based alloy used in nuclear high-temperature environment of the nuclear reactor provided by the invention has excellent corrosion resistant performance; and compared with ZIRLO alloy of the prior art, the alloy has more excellent corrosion resistant performance in high-temperature pure water and high-temperature lithium-containing water, and is suitable for corrosion-resistant zirconium alloys of fuel rod cladding materials, grillwork stripes and structural parts under relatively high fuel consumption of the nuclear reactor.

Description

technical field [0001] The invention relates to the field of zirconium alloy materials, in particular to a corrosion-resistant Cu-containing zirconium alloy that can be used as fuel rod cladding materials, grid strips and structural parts in pressurized water reactor nuclear power plants with relatively high burnup. Background technique [0002] Zirconium alloy has small thermal neutron absorption cross section, high thermal conductivity, good mechanical properties, good processing performance and the same UO 2 Good compatibility, especially for high-temperature water and high-temperature steam, it also has good corrosion resistance and sufficient thermal strength, so it is widely used as cladding material and core structure material of water-cooled power reactors. With the development of nuclear power reactor technology in the direction of increasing fuel burnup and prolonging the refueling cycle, higher requirements are put forward for zirconium alloys for fuel element cla...

Claims

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Application Information

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IPC IPC(8): C22C16/00
CPCC22C16/00
Inventor 曾奇锋陈磊陈芙梁朱丽兵李聪
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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