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Electrolyte and its use and method for preparing nuclear fuel rod zirconium alloy cladding micro-arc oxidation film

A micro-arc oxidation, nuclear fuel rod technology, applied in electrolytic coatings, surface reaction electrolytic coatings, coatings, etc., to achieve the effects of improving corrosion resistance, wide solute sources, and prolonging service life

Active Publication Date: 2015-08-19
SUZHOU NUCLEAR POWER RES INST +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

At present, there is still a lack of an electrolyte and micro-arc oxidation process suitable for the preparation of nuclear fuel rod cladding protective film

Method used

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  • Electrolyte and its use and method for preparing nuclear fuel rod zirconium alloy cladding micro-arc oxidation film
  • Electrolyte and its use and method for preparing nuclear fuel rod zirconium alloy cladding micro-arc oxidation film

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0034] In this example, the treated zirconium alloy cladding material is a Zr-1Nb sample.

[0035] First, pre-treat the sample. The processing procedure is as follows: grind the surface of the sample with 200#, 400#, 600#, and 800# sandpaper; mechanically polish the polished sample, and use emery as the polishing agent; mechanically polish Chemical polishing is carried out after completion, and the reagent for chemical polishing is HNO 3 :HCl:H 2 O=4.5:4.5:1 (volume ratio) polishing solution, polishing time 10s; after chemical polishing is completed, use alcohol and ultrasonic cleaning, and finally, wash the surface of the sample with deionized water several times to remove the acid remaining on the surface . Put the chemically polished zirconium alloy into a vacuum furnace for thermal annealing treatment, the annealing temperature is 580° C., and the time is 2 hours.

[0036]Secondly: configure the electrolyte: the electrolyte is uniformly mixed with sodium carbonate, lith...

Embodiment 2

[0040] According to the same method as in Example 1, the Zr-1Nb sample is pretreated, the electrolyte is prepared, the zirconium alloy is subjected to micro-arc oxidation treatment, and finally the hole sealing treatment is performed. The difference is that in this example, the content of sodium carbonate in the electrolyte is 10g / L, the content of lithium hydroxide is 5g / L, and the content of glycerin is 30ml / L. The micro-arc oxidation treatment was carried out for 15 minutes under the condition that the forward voltage was 500V and the negative voltage was 60V.

[0041] Through the above steps, a zirconium alloy workpiece whose surface is covered with a layer of uniform and smooth micro-arc oxidation film is finally obtained, denoted as A2.

Embodiment 3

[0043] According to the same method as in Example 1, the Zr-1Nb is pretreated, the electrolyte is prepared, the surface of the zirconium alloy is subjected to micro-arc oxidation treatment, and finally the hole sealing treatment is performed. The difference is that in this example, the content of sodium carbonate in the electrolyte is 6g / L, the content of lithium hydroxide is 7g / L, and the content of glycerin is 50ml / L. The forward voltage of micro-arc oxidation treatment was 400V, and the negative voltage was 50V, and the treatment was carried out under these conditions for 15 minutes.

[0044] Through the above steps, a zirconium alloy workpiece whose surface is covered with a layer of uniform and smooth micro-arc oxidation film is finally obtained, denoted as A3.

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Abstract

The invention relates to an electrolyte for preparing a micro-arc oxidation film on a surface of zirconium or a zirconium alloy, a method for performing micro-arc oxidation on the surface of the zirconium or the zirconium alloy by using the electrolyte, as well as application of the electrolyte in preparing a micro-arc oxidation film on the surface of the zirconium alloy cladding of a nuclear fuel rod. The electrolyte is a mixed aqueous solution which is mixed with 5g / L-15g / L of sodium carbonate, 2g / L-12g / L of lithium hydroxide and 30ml / L-60ml / L of glycerin. The using environment for the cladding of the nuclear fuel rod in a reactor is fully taken into account, and the electrolyte for micro-arc oxidation of the zirconium alloy and an oxidation technology are selected reasonably, so that after a cladding material of the zirconium alloy is treated by micro-arc oxidation, the resistance to high temperature, high pressure and water corrosion is increased greatly.

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 material surface modification and is mainly suitable for improving the resistance of nuclear fuel rod zirconium alloy cladding in high-temperature and high-pressure water environments. corrosion performance. Background technique [0002] Zirconium alloys have small thermal neutron absorption cross-sections, good high-temperature water corrosion resistance and high-temperature mechanical properties, and are widely used as cladding materials for nuclear fuel rods and structural components for reactor cores. When used as cladding for nuclear fuel rods, zirconium alloys must transmit energy on the one hand, and at the same time avoid contact between the fuel and the coolant, contain radioactive fission products, and prevent the coolant from being contaminated...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C25D11/26
Inventor 束国刚王荣山咸春宇薛文斌邹志锋贾兴娜杜建成翁立奎刘彦章
Owner SUZHOU NUCLEAR POWER RES INST
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