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FeCrAl alloy and T91 ferrite/martensite heat-resistant steel composite tube for nuclear reactor nuclear fuel cladding and manufacturing method for FeCrAl alloy and T91 ferrite/martensite heat-resistant steel composite tube

A nuclear reactor and ferrite technology, applied in heat treatment equipment, heat treatment furnaces, manufacturing tools, etc., can solve problems such as uneven thickness of the inner and outer layers, poor quality of the inner surface of the tube billet, etc., to improve the ability of anti-radiation, The effect of improving the ability to resist LOCA accidents and improving the ability to resist high-temperature oxidation

Active Publication Date: 2019-07-05
INST OF METAL RESEARCH - CHINESE ACAD OF SCI +3
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

The problem with this method is that the thickness of the inner and outer layers is not uniform, and the quality of the inner surface of the tube blank is not good.

Method used

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  • FeCrAl alloy and T91 ferrite/martensite heat-resistant steel composite tube for nuclear reactor nuclear fuel cladding and manufacturing method for FeCrAl alloy and T91 ferrite/martensite heat-resistant steel composite tube
  • FeCrAl alloy and T91 ferrite/martensite heat-resistant steel composite tube for nuclear reactor nuclear fuel cladding and manufacturing method for FeCrAl alloy and T91 ferrite/martensite heat-resistant steel composite tube
  • FeCrAl alloy and T91 ferrite/martensite heat-resistant steel composite tube for nuclear reactor nuclear fuel cladding and manufacturing method for FeCrAl alloy and T91 ferrite/martensite heat-resistant steel composite tube

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Embodiment 1

[0050] The metal seamless composite pipe of this embodiment is a three-layer composite of FeCrAl (outer layer) / Fe alloy (transition layer) / T91 (inner layer), and the FeCrAl alloy composition is: Cr 12.5wt%, Al 4.2wt%, Nb 0.3wt% %, Fe surplus; transition layer is ferroalloy divided into: C 0.01wt%, Nb 0.3wt%, Si 0.1wt%, Mn0.2wt%, Fe surplus; inner layer is T91 (P91) alloy. Its specification is Φ9.5mm (outer diameter) × 0.5mm (wall thickness), and the main preparation process is as follows:

[0051] (1) Tube blank polishing: Polish the inner and outer surfaces of the outer tube, transition tube, and inner tube to Ra0.1μm respectively, and the gap between the tubes in each layer is about 0.1mm.

[0052] (2) Tube billet assembly and packaging: the polished FeCrAl, Fe alloy, and T91 tube billet are drawn and assembled with mandrel layer by layer. After the outer tube and the inner tube are assembled, the shrinking process of the tube head is carried out at the same time. Then dra...

Embodiment 2

[0065] The metal seamless composite pipe of this embodiment is a three-layer composite of FeCrAl (outer layer) / Fe alloy (transition layer) / T91 (inner layer), and the FeCrAl alloy composition is: Cr 13.1wt%, Al 4.0wt%, V 0.2wt% %, Fe surplus; transition layer is ferroalloy divided into: C 0.005wt%, V 0.3wt%, Si 0.15wt%, Mn0.2wt%, Fe surplus; inner layer is T91 (P91) alloy. Its specification is Φ9.5mm (outer diameter) × 0.5mm (wall thickness), and the main preparation process is as follows:

[0066] (1) Polishing of the tube blank, polishing the inner and outer surfaces of the outer tube, transition tube, and inner tube respectively to Ra0.1μm, and the gap between the tubes of each layer is -0.1mm.

[0067] (2) The tube blank is assembled and packaged. The Fe alloy (transition layer) tube is immersed in a low-temperature liquid nitrogen solution. The transition tube shrinks at low temperature. After cleaning, it is assembled into the FeCrAl (outer layer) tube. When it returns t...

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Abstract

The invention relates to the field of fuel cladding tubes with relatively high neutron irradiation resistance, corrosion resistance and high temperature resistance in a nuclear reactor, in particularto a FeCrAl alloy and T91 ferrite / martensite heat-resistant steel composite tube for nuclear reactor nuclear fuel cladding and a manufacturing method for the FeCrAl alloy and T91 ferrite / martensite heat-resistant steel composite tube. The inner layer is a ferrite / martensite heat-resistant steel material, the outer layer is a FeCrAl alloy material, and an iron-based material auxiliary layer is arranged between the inner layer and the outer layer. The manufacturing method for the FeCrAl alloy and T91 ferrite / martensite heat-resistant steel composite tube comprises the following steps: surface polishing of seamless composite tube blank, degassing, assembling and packaging of seamless composite tube blank, thermal deformation processing metallurgical compounding, annealing thermal treatment, cold-rolled cold-drawing and intermediate annealing, final thermal treatment, straightening, cleaning and finished product inspecting. The method is characterized in that the outer layer, an intermediate transition layer and an inner-layer tube are assembled, are assembled and packaged into seamless composite tube blank after gas exhaustion, and are sealed by a welding end head; after being heated,the metallurgical compounded seamless composite tube blank formed by thermal deformation processing is finally subjected to cold-deformation processing to form a finished product of a needed specification.

Description

technical field [0001] The invention relates to the field of fuel cladding tubes exhibiting high neutron radiation resistance and corrosion resistance in water-cooled nuclear reactors, in particular to a FeCrAl alloy and T91 ferrite / martensitic corrosion resistance for nuclear fuel cladding of nuclear reactors. Hot steel metal seamless composite pipe structure and its preparation method. Background technique [0002] Zr alloys were and are important structural materials for nuclear reactors in the past and present. They have good corrosion resistance and neutron radiation resistance in high-pressure water and steam at 300-400 ° C. Some newly developed Zr alloys (such as: ZIRLO, M5 , E635, etc.) are used as cladding and structural components of high burnup fuel assemblies for pressurized water reactors and boiling water reactors. The research content of advanced zirconium alloys includes: corrosion resistance, mechanical properties, water corrosion properties, radiation grow...

Claims

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Application Information

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IPC IPC(8): C22C38/26C22C38/24C22C38/02C22C38/04B21C37/06C22C38/06C21D1/25C21D1/30C21D8/10C21D9/08
CPCB21C37/06C21D1/25C21D1/30C21D8/105C21D9/085C21D2211/005C21D2211/008C22C38/02C22C38/04C22C38/06C22C38/24C22C38/26
Inventor 韩维新杨英曲顺德翟剑晗韩建李锐韩君平李依依
Owner INST OF METAL RESEARCH - CHINESE ACAD OF SCI
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