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Electrolyte for preparation of protective film for Zr alloy cladding and micro-arc oxidation process

A micro-arc oxidation, zirconium alloy technology, applied in electrolytic coatings, surface reaction electrolytic coatings, coatings, etc., to achieve good ionic conductivity and chemical stability, a wide range of solute sources, and improve corrosion resistance.

Inactive Publication Date: 2013-12-25
BEIJING NORMAL UNIVERSITY +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

At present, there is still a lack of an electrolyte and micro-arc oxidation process for the preparation of zirconium alloy cladding protective film that can meet the use environment of nuclear reactor fuel rod cladding and the high temperature and high pressure corrosion protection requirements.

Method used

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  • Electrolyte for preparation of protective film for Zr alloy cladding and micro-arc oxidation process
  • Electrolyte for preparation of protective film for Zr alloy cladding and micro-arc oxidation process

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Abstract

The invention discloses an electrolyte for micro-arc oxidation surface treatment of a Zr alloy cladding of a nuclear fuel rod. The electrolyte is a water solution containing rare earth salt, glycerin, sodium hydroxide and potassium hydroxide. The invention also discloses a preparation process of micro-arc oxidation film on surface of zirconium alloy cladding of the nuclear fuel rod, and the preparation process uses the electrolyte provided by the invention. Through the micro-arc technology provided by the invention, a layer of compact oxidation film is generated on the surface of a zirconium alloy cladding tube in advance, so as to corrosion resistance of the zirconium alloy cladding of the nuclear fuel rod in high temperature and high pressure water environment, and prolong the usage life of the nuclear fuel assemblies in a reactor.

Description

technical field [0001] The invention relates to an electrolyte and a process for preparing a protective film on the surface of nuclear fuel rod cladding by using micro-arc oxidation technology, which belongs to the field of zirconium alloy materials and material surface modification, and is mainly suitable for improving the temperature of nuclear fuel rod zirconium alloy cladding in high temperature and high pressure water. Corrosion resistance in the environment. Background technique [0002] Zirconium has a small thermal neutron absorption cross-section, good high-temperature water corrosion resistance and high-temperature mechanical properties, so zirconium alloys are widely used as cladding materials for nuclear fuel rods and structural components of reactor cores in nuclear power reactors. When zirconium alloy is used as the cladding of nuclear fuel, on the one hand, it is necessary to transfer the heat energy released during nuclear fuel fission to the coolant, and at ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C25D11/26
Inventor 薛文斌束国刚咸春宇王荣山邹志锋杜建成华铭施修龄刘彦章翁立奎贾兴娜
Owner BEIJING NORMAL UNIVERSITY
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