Gd-containing duplex stainless steel with excellent neutron absorption performance and preparation method of Gd-containing duplex stainless steel

Abstract

The invention discloses Gd-containing duplex stainless steel with excellent neutron absorption performance and a preparation method of the Gd-containing duplex stainless steel, and belongs to the technical field of duplex stainless steel. The stainless steel comprises the following components of, in percentage by mass, 0.02-0.06 wt.% of C, 23.00-26.00 wt.% of Cr, 4.00-8.00 wt.% of Ni, less than or equal to 1.00 wt.% of Si, 0.50-3.00 wt.% of rare earth Gd, 1.00-2.00 wt.% of Mn, 1.00-2.00 wt.% of Mo, less than 0.10 wt.% of Al, less than 0.002 wt.% of O, less than 0.02 wt.% of N, less than 0.002 wt.% of S, less than 0.010 wt.% of P, and the balance Fe. According to the Gd-containing duplex stainless steel with the excellent neutron absorption performance and the preparation method of the Gd-containing duplex stainless steel, the Gd-containing duplex stainless steel has excellent neutron and gamma ray comprehensive shielding performance and thermal machining crack resistance, also has good mechanical properties, can be directly used as a structural part for design and manufacturing of neutron shielding products, and can realize functional structure integrated design.

Description

technical field [0001] The invention relates to the technical field of nuclear radiation shielding protection, in particular to a Gd-containing duplex stainless steel with excellent neutron absorption performance and a preparation method thereof. Background technique [0002] With the rapid development of nuclear power in our country, the increasing amount of spent fuel and radioactive waste is a serious problem facing our country. It is estimated that more than 20,000 tons will be produced by the end of 2030. In addition to strong α, β, and γ rays, spent fuel and radioactive waste also have very strong neutron radiation. Therefore, every ton of spent fuel and radioactive waste transported from a nuclear power plant to a storage or reprocessing plant, The transportation container needs to be 6 times or 20 times that of the spent fuel, which is inefficient. Even so, most of the storage and transportation containers have to be imported, and the quantity is insufficient. On the...

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Problems solved by technology

Moreover, there are some common technical problems in B-containing neutron shielding materials, that is, natural B itself has limited ability to absorb neutrons, and it is necessary to add 10B or add a large amount of B by powder metallurgy. 4 C to meet the function of absorbing neutrons, resulting in a substantial increase in manufacturing costs

In addition, in order to meet the neutron absorption performance, a large amount of B content will cause fatal damage to the processing performance and mechanical properties of the material, which restricts the application of high B content materials to achieve functional / structural integration of neutron shielding materials

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