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Production method of protection film for nuclear fuel rod zirconium alloy cladding laser welded joint

A laser welding and nuclear fuel rod technology, applied in electrolytic coatings, nuclear power generation, surface reaction electrolytic coatings, etc., can solve problems such as preferential corrosion of zirconium alloy welded joints, prolong service life, improve corrosion resistance, and prevent preferential corrosion. Effect

Inactive Publication Date: 2015-10-28
BEIJING NORMAL UNIVERSITY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] The technical problem to be solved by the present invention is to solve the problem of preferential corrosion of zirconium alloy welded joints in a high-temperature water environment, and provide a preparation method for the surface protective film of laser welded joints of zirconium alloy cladding of nuclear fuel rods, which can prolong the life of zirconium alloy cladding of nuclear fuel rods. The service life of the reactor in high temperature and high pressure water environment

Method used

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  • Production method of protection film for nuclear fuel rod zirconium alloy cladding laser welded joint
  • Production method of protection film for nuclear fuel rod zirconium alloy cladding laser welded joint
  • Production method of protection film for nuclear fuel rod zirconium alloy cladding laser welded joint

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0019] The sample is a Zr-1Nb alloy laser welding sample.

[0020] Pretreatment: Laser welding samples of zirconium alloy with 80 # -2000 # After the sandpaper is polished step by step, it is placed in acetone and ultrasonically cleaned to remove oil.

[0021] Configuration of electrolyte: The electrolyte is an aqueous solution composed of sodium phosphate, potassium hydroxide, and glycerin, and the composition is 2g / L sodium phosphate, 3g / L potassium hydroxide, and 2g / L glycerin.

[0022] The Zr-1Nb alloy laser welding sample was put into the prepared electrolyte, the laser welding sample was used as the anode, the stainless steel electrolytic cell was used as the cathode, the positive voltage was +360V, the negative voltage was -150V, and the micro-arc oxidation treatment was 30min.

[0023] The Zr-1Nb alloy welded specimens after micro-arc oxidation were immersed in pure water at 95°C for 6 minutes, sealed, and then dried with hot air at 45°C.

[0024] After the above steps, the zirc...

Embodiment 2

[0026] The surface pretreatment of the Zr-1Nb sample was carried out in the same method as in Example 1, the electrolyte was prepared, and the zirconium alloy laser welding sample was subjected to micro-arc oxidation treatment, and finally the sealing treatment was carried out.

[0027] Among them, the electrolyte uses: 6g / L sodium phosphate, 1g / L potassium hydroxide, 2g / L glycerin.

[0028] The Zr-1Nb alloy laser welding sample was put into the prepared electrolyte, the laser welding sample was used as the anode, the stainless steel electrolytic cell was used as the cathode, the positive voltage was +340V, the negative voltage was -150V, and the treatment time was 30 minutes.

[0029] Finally, a laser welding sample M2 of zirconium alloy treated by micro-arc oxidation is obtained.

Embodiment 3

[0031] With reference to the method of Example 1, the Zr-1Nb sample was subjected to surface pretreatment, electrolyte was prepared, and the zirconium alloy laser welded sample was subjected to micro-arc oxidation treatment, and finally the sealing treatment was performed.

[0032] Configuration electrolyte: 4g / L sodium phosphate, 3g / L potassium hydroxide, 2g / L glycerin.

[0033] The Zr-1Nb alloy laser welding sample was put into the prepared electrolyte, the laser welding sample was used as the anode, and the stainless steel electrolytic cell was used as the cathode. The positive voltage was +400V, the negative voltage was -100V, and the treatment time was 30min.

[0034] Finally, a laser welding sample M3 of the zirconium alloy treated by micro-arc oxidation is obtained.

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Abstract

The invention discloses an electrolyte formula and a method for zirconium alloy laser welded joint micro-arc oxidation. The micro-arc oxidation method is adopted to produce an oxide film on the surface of a zirconium alloy laser welded workpiece in order to solve the problem of corrosion protection of welded joints of two ends of a nuclear fuel rod zirconium alloy cladding. The above electrolyte is an aqueous solution composed of sodium phosphate, potassium hydroxide and glycerin. Micro-arc oxidation electrical parameters comprise a positive voltage of +200 ~ +500 V, a negative voltage of -50 ~ -200V and an oxidation time of 10-60min, and the thickness of the produced oxide film is 10-50[mu]m. The compact pre-oxidized film is generated on the surface of the zirconium alloy laser welded joint through the micro-arc oxidation method, so the corrosion resistance of the nuclear fuel rod zirconium alloy cladding laser welded joint in high-temperature and high-pressure water environment is greatly improved, and the service life of a reactor fuel assembly is prolonged.

Description

Technical field [0001] The invention relates to a metal material surface modification treatment technology, in particular to a process method for preparing electrolyte and micro-arc oxidation on the surface of a zirconium alloy laser welded joint, and is mainly suitable for improving the corrosion resistance of a nuclear fuel rod zirconium alloy cladding laser welded joint. Extend the service life of the reactor fuel assembly. Background technique [0002] The thermal neutron absorption section of zirconium is small, and it has good high temperature water corrosion resistance and high temperature mechanical properties. Therefore, zirconium alloy is widely used as the cladding material of nuclear fuel rods in nuclear power reactors. When zirconium alloy is used as the cladding of nuclear fuel, on the one hand, it must transfer the heat energy released during nuclear fuel fission to the coolant, and at the same time avoid contact between the fuel and the coolant, contain the radioa...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C25D11/26G21C3/07
CPCY02E30/30
Inventor 薛文斌曲尧贾兴娜阳超林杜建成华铭
Owner BEIJING NORMAL UNIVERSITY