Preparation method of ferrite martensite steel ladle shell pipe

Abstract

The invention belongs to the technical field of fourth-generation lead bismuth cooling fast reactor structural materials, and particularly relates to a preparation method of a ferrite martensite steel ladle shell pipe. The ferrite martensite steel ladle shell pipe comprises the components of 0.15%-0.25% of C, 0.30%-0.8% of Mn, 0.40%-1.20% of Si, 10.5%- 12.5% of Cr, 1.0%-2.5% of W, 0.10%-0.40% of V, 0.10%-0.40% of Ta, 0.005%-0.08% of Zr, 0.005%-0.05% of La, 0.008%-0.04% of N, and balance Fe and impurities. The preparation method of the ferrite martensite steel ladle shell material comprises the following process steps of (1) determining the alloy components; (2) smelting; (3) casting; (4) forging; (5) extruding; (6) pipe blank machining and heat treatment; (7) multi-pass cold rolling and intermediate heat treatment of the alloy; and (8) final heat treatment of the pipe. According to the preparation method of the ferrite martensite steel ladle shell pipe, through the innovative component design, the optimized pipe machining deformation process and the heat treatment technology, the microstructure of the material is improved, grains are refined, and therefore the comprehensive performance of the alloy is improved.

Description

technical field [0001] The invention belongs to the technical field of fourth-generation lead-bismuth cooled fast reactor structural materials, and in particular relates to a method for preparing ferritic martensitic steel cladding pipes. Background technique [0002] Austenitic stainless steel 304 and 316 are used as the first-generation cladding materials for sodium-cooled fast reactors because of their good corrosion resistance and thermal creep properties, but when the irradiation dose reaches 50dpa (displacements per atom), they will Excessive swelling is produced. After one incubation period, the radiation swelling rate of austenitic stainless steel is 1% for each additional dpa. The radiation swelling during the service of the material can be reduced by adding stabilizing elements and introducing cold working, such as the application in the United States Ti is used as a stabilizing element and the cold-worked D9 alloy. The 15-15Ti alloy used in France as the cladding ...

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Problems solved by technology

[0002] Austenitic stainless steel 304 and 316 are used as the first-generation cladding materials for sodium-cooled fast reactors because of their good corrosion resistance and thermal creep properties, but when the irradiation dose reaches 50dpa (displacements per atom), they will Excessive swelling is produced. After one incubation period, the radiation swelling rate of austenitic stainless steel is 1% for each additional dpa. The radiation swelling during the service of the material can be reduced by adding stabilizing elements and introducing cold working, such as the application in the United States Ti is used as a stabilizing element and the cold-worked D9 alloy. The 15-15Ti alloy used in France as the cladding material has reached 130dpa fast neutron irradiation dose, but these steels show insufficient ductility after exceeding 100dpa. The fourth In order to achieve higher burnup, lead-bismuth-substitute cooled fast reactors require the anti-neutron radiation dose of the cladding material to reach more than 200dpa

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