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Zirconium alloy used as structural material of nuclear pressurized water reactor

A technology for pressurized water reactors and structural materials, applied in the field of zirconium alloy materials, can solve problems such as inability to meet requirements, and achieve the effects of improving creep performance, improving corrosion resistance, and excellent comprehensive performance

Active Publication Date: 2013-01-16
SUZHOU NUCLEAR POWER RES INST +1
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

At present, the most mature and widely used zirconium alloys are called Zr-2 and Zr-4 alloys. However, with the development of nuclear fuel assemblies in the direction of long life and high burnup, zirconium-based alloys as reactor structural materials are required It must have better comprehensive properties such as corrosion resistance, creep resistance, and radiation growth resistance. At this point, Zr-2 and Zr-4 alloys can no longer meet the requirements

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  • Zirconium alloy used as structural material of nuclear pressurized water reactor

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Embodiment Construction

[0012] The present invention will be further described below in conjunction with specific embodiment, but the present invention is not limited to following embodiment:

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Abstract

The invention discloses a zirconium alloy used as a nuclear pressurized water reactor structural material. Based on the total weight of the zirconium alloy, the zirconium alloy is composed of the following components: Nb0.25%-0.4%, Fe0.3 %~0.45%, Cr0.2%~0.3%, S30ppm~100ppm, O600~1200ppm, C≤100ppm, N≤80ppm and Zr balance, wherein, the weight ratio of Nb to Fe≤1, the weight ratio of Fe to Cr It is 1.4~1.6:1. The invention optimizes the traditional Zr-Nb alloy formula, which not only improves the corrosion resistance of the zirconium alloy, but also improves the creep performance and welding performance of the alloy. requirements.

Description

technical field [0001] The invention relates to the field of zirconium alloy materials, in particular to a zirconium alloy that can be used as a structural material for nuclear pressurized water reactors. Background technique [0002] The thermal neutron absorption cross section of zirconium is very small, and has good high temperature water corrosion resistance and mechanical properties, so zirconium alloys are widely used as cladding materials for fuel rods and structural elements of nuclear reactor cores in water-cooled nuclear reactors. With the development of nuclear power reactor technology in the direction of increasing fuel consumption, reducing fuel cycle costs, increasing reactor thermal efficiency, and improving safety and reliability, the corrosion resistance, hydrogen absorption performance, and Higher requirements are put forward for mechanical properties and radiation dimensional stability. Creep and fatigue will occur in fuel elements under service condition...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C3/07C22C16/00
CPCY02E30/30
Inventor 王荣山翁立奎耿建桥张晏玮王锦红
Owner SUZHOU NUCLEAR POWER RES INST
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