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Ferrite martensite steel ladle shell material and preparation method thereof

A martensitic steel and cladding material technology, applied in the field of fourth-generation lead-bismuth cooled fast reactor structural materials, can solve the problems of insufficient ductility, high fuel consumption, etc., and achieve improved high temperature performance and neutron radiation resistance performance Effect

Inactive Publication Date: 2021-04-23
NUCLEAR POWER INSTITUTE OF CHINA
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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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  • Ferrite martensite steel ladle shell material and preparation method thereof
  • Ferrite martensite steel ladle shell material and preparation method thereof
  • Ferrite martensite steel ladle shell material and preparation method thereof

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[0066] A ferritic martensitic steel cladding material, the alloy comprising:

[0067] C: 0.08~0.16wt%, Mn: 0.30~0.8wt%, Si: 0.50~1.20wt%, Cr: 8.5~10.5wt%, W: 1.0~2.5wt%, V: 0.10~0.40wt%, Ta: 0.10-0.40wt%, Zr: 0.005-0.08wt%, La: 0.005-0.05wt%, N: 0.008-0.04wt%, and the rest are Fe and impurities.

[0068] The C, N content and Ta, V, Zr content in the alloy satisfy the following quantitative relationship:

[0069] 1.5 times (C+N) content≤(Ta+V+Zr) content≤3 times (C+N) content.

[0070] The impurities in the alloy and their content control meet the following conditions: S<0.003wt%, P<0.008wt%, B<0.01wt%, O<0.002wt%, H<0.001wt%.

[0071] As a further optimized technical solution, except for impurities, the main component of the alloy is Fe-9Cr-1.5W-0.5Mn-0.12C-0.15Ta-0.2V-0.02N-0.01Zr-0.03La-0.6Si.

[0072] A method for preparing a ferritic martensitic steel cladding material as described above, comprising the following process steps:

[0073] (1) Melting

[0074] (1.1) Carr...

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Abstract

The invention belongs to the technical field of fourth-generation lead bismuth cooling fast reactor structural materials, and particularly relates to a ferrite martensite steel ladle shell material and a preparation method thereof. The ferrite martensite steel ladle shell material comprises the components of 0.08wt%-0.16wt% of C, 0.30wt%- 0.8wt% of Mn, 0.50wt%-1.20wt% of Si, 8.5wt%-10.5wt% of Cr, 1.0wt%-2.5wt% of W, 0.10wt%-0.40wt% of V, 0.10wt%-0.40wt% of Ta, 0.005wt%-0.08wt% of Zr, 0.005wt%-0.05wt% of La, 0.008wt%-0.04wt% of N, and the balance Fe and impurities. The preparation method of the ferrite martensite steel ladle shell material comprises the following process steps of (1) smelting; (2) casting; (3) forging; (4) extruding; (5) pipe blank machining and heat treatment; (6) multi-pass cold rolling and intermediate heat treatment of the alloy; and (7) final heat treatment of the pipe. According to the ferrite martensite steel ladle shell material and the preparation method thereof, 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 ferritic martensitic steel cladding material and a preparation method thereof. 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 a...

Claims

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Application Information

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IPC IPC(8): C22C38/04C22C38/02C22C38/22C22C38/24C22C38/26C22C38/28C22C33/04C21D1/28C21D1/773C21D9/08B23P15/00G21C15/14
CPCY02E30/30
Inventor 潘钱付邱绍宇王辉刘超红吴裕卓洪赵勇
Owner NUCLEAR POWER INSTITUTE OF CHINA
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