Neutron absorbing material and preparation method thereof

A technology for absorbing materials and neutron absorbers, applied in the field of neutron absorbing materials and their preparation, to achieve the effects of improved absorption capacity, excellent mechanical properties, and high density

Active Publication Date: 2015-12-30
HARBIN INST OF TECH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0009] The present invention aims to solve the problem that existing spent fuel shielding materials cannot improve the plasticity of the composite materi

Method used

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  • Neutron absorbing material and preparation method thereof
  • Neutron absorbing material and preparation method thereof

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specific Embodiment approach 1

[0020] Specific Embodiment 1: In this embodiment, a neutron absorbing material is made of 10% to 20% boron carbide, 1% to 2% neutron absorber and 78% to 89% aluminum-containing material by volume fraction; Boron is boron carbide particles with a particle size of 17.5 μm or boron carbide particles with a particle size of 5 μm; the aluminum-containing material is aluminum or aluminum alloy.

[0021] The neutron absorbing material of this embodiment has a high density, and since the boron carbide content is about 10% to 20%, it not only has a good reinforcing effect, but also can exert the plasticity of the aluminum alloy, and the composite material has good plasticity and is easy to process Forming; at the same time, due to the addition of element particles with a high neutron absorption cross section in the neutron absorbing material, the neutron absorbing ability of the composite material is improved; the prepared neutron absorbing material has excellent mechanical properties, ...

specific Embodiment approach 2

[0022] Specific embodiment 2: The difference between this embodiment and specific embodiment 1 is that the neutron absorbing material is made of 14% to 16% boron carbide, 1% neutron absorber and 83% to 85% aluminum-containing materials by volume fraction . Others are the same as the first embodiment.

specific Embodiment approach 3

[0023] Embodiment 3: The difference between this embodiment and Embodiment 1 or 2 is that the neutron absorbing material is made of 15% boron carbide, 1% neutron absorber and 84% aluminum-containing material by volume fraction. Others are the same as those in Embodiment 1 or 2.

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Abstract

A neutron absorbing material and its preparation method relate to a neutron absorbing material and its preparation method. The invention aims to solve the problem that existing spent fuel shielding materials cannot ensure neutron shielding property of a composite material, and plasticity of a composite material can be enhanced. The neutron absorbing material is prepared from, by volume, 10-20% of boron carbide, 1-2% of a neutron absorber and 78-89% of aluminium or aluminium alloy. The preparation method comprises the following steps: 1, weighing; 2, drying; 3, ball-milling and mixing; and 4, cold pressing for blank-making and hot pressed sintering. The neutron absorbing material prepared in the invention has high shielding property, has good plasticity, is easy for machine-shaping, can meet requirements of densification and long-term tendency for spent fuel storage, and is an ideal spent fuel storage grid material. The neutron absorbing material of the invention is used in the field of neutron radiation shielding in nuclear industry.

Description

technical field [0001] The invention relates to a neutron absorbing material and a preparation method thereof. Background technique [0002] After nuclear fuel is used, it will become spent fuel, which has a high neutron radiation effect. If it is not handled properly, it will cause serious radiation pollution to the surrounding environment. With the rapid development of the nuclear industry, more and more nuclear power plants have been put into use one after another, which will also lead to the generation of a large amount of spent fuel. Due to the limited storage space and the extension of the service life of the reactor, the nuclear industry is facing high density of spent fuel. , long-term storage challenges, so higher requirements for the use of spent fuel storage grids are put forward, that is, strong neutron absorption capacity, which can meet the requirements of high-density and long-term storage of spent fuel. Therefore, the development of materials with excellent ...

Claims

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Application Information

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IPC IPC(8): C22C21/00C22C32/00C22C1/05
Inventor 武高辉姜龙涛徐中国康鹏超陈国钦张强修子扬苟华松宫灯
Owner HARBIN INST OF TECH
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