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Method for improving lead bismuth alloy corrosion resistance of nuclear power structural material

A technology for structural materials and corrosion performance, applied in the field of improving the anti-corrosion performance of lead-bismuth alloys for nuclear power structural materials, can solve the problems of oxygen partial pressure and oxygen content, high cost of new material development, weakened material properties, etc., to achieve improved lead resistance Corrosion properties of bismuth alloys, easy control of the process, and low cost

Inactive Publication Date: 2017-02-01
INST OF METAL RESEARCH - CHINESE ACAD OF SCI
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Problems solved by technology

However, the above two methods have certain disadvantages: the control of oxygen partial pressure and oxygen content is relatively difficult, and the corrosion resistance of lead-bismuth alloys of nuclear power structural materials cannot be fundamentally solved; the adjustment of low-activation ferrite / martensite The chemical composition of steel may lead to the weakening of other properties of the material, such as neutron radiation resistance, etc.; and the development cost of new materials is high and the cycle is long

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  • Method for improving lead bismuth alloy corrosion resistance of nuclear power structural material
  • Method for improving lead bismuth alloy corrosion resistance of nuclear power structural material
  • Method for improving lead bismuth alloy corrosion resistance of nuclear power structural material

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Embodiment 1

[0040] This embodiment selects low-activation ferrite / martensitic steel (11Cr-WVTaSi) as the object, and its chemical composition is (wt.%): C 0.23%, Si 1.15%, Mn 0.40%, S 0.01%, P 0.01 %, Cr 10.7%, Ni 0.2%, W1.7%, Ta 0.05%, V 0.35%, Nb 0.05%, B 0.005%, Fe balance. The low-activation ferrite / martensitic steel is supplied in tempered state, the diameter of the rotary test piece is 10mm, and the surface of the test piece is in the turned state. The corrosion medium is liquid lead-bismuth alloy (eutectic, LBE), the corrosion temperature is 550°C, and the corrosion time is 3500 hours.

[0041] The surface nano-processing method of the present invention is used to perform surface nano-processing on low-activation ferrite / martensitic steel. The material of the hard ball of the surface nano-processing head is WC / Co, and the diameter of the hard ball is 8mm. Rotation speed v of low activation ferritic / martensitic steel rotary specimen 1 =3×10 4 mm / min; the axial feed speed v of th...

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Abstract

The invention discloses a method for improving the lead bismuth alloy corrosion resistance of a nuclear power structural material. According to the method for improving the lead bismuth alloy corrosion resistance of the nuclear power structural material, surface treatment is conducted on the nuclear power structural material through the surface nanocrystallization technology, the surface of the nuclear power structural material is made to form a gradient nano-structure and a structure refined structural layer, the nuclear power structural material obtained after surface nanocrystallization generates a compact passivation coating with the thickness smaller than 5 [mu]m in liquid-state lead bismuth alloy, the passivation coating relieves the corrosion of the nuclear power structural material in the liquid-state lead bismuth alloy, and therefore the lead bismuth alloy corrosion resistance of the nuclear power structural material is improved. After surface treatment, the thickness of the surface gradient nanometer crystals and the structure refined structural layer of the nuclear power structural material reaches over 150[mu]m, the surface crystallite dimension is refined to be below 50 nm, and the surface roughness Ra is controlled to be below 0.3 [mu]m. After the nuclear power structural material is treated by the adoption of the method, compared with the nuclear power structural material which is not treated, the lead bismuth alloy corrosion resistance of the nuclear power structural material can be significantly improved.

Description

technical field [0001] The invention relates to the technical field of nuclear power structural materials, in particular to a method for improving the anti-corrosion performance of lead-bismuth alloy of nuclear power structural materials. Background technique [0002] As a clean energy, nuclear energy is getting more and more attention and development, and the ensuing nuclear waste disposal has become an urgent problem to be solved, and it has become one of the restrictive factors for the sustainable development of nuclear energy. The accelerator-driven subcritical system (ADS system) based on separation and transmutation technology is a new type of nuclear energy system for nuclear waste transmutation and energy generation, and has become one of the important technical directions for the development of new generation nuclear energy. The structural materials of the ADS system are used in harsh environments, and they need to have high temperature resistance, radiation resista...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C21D7/04
CPCC21D7/04
Inventor 张伟华王镇波卢柯
Owner INST OF METAL RESEARCH - CHINESE ACAD OF SCI
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