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A kind of al-b4c-b neutron absorbing material and preparation method thereof

An absorbing material, al-b4c-b technology, applied in radiation protection neutron absorbing materials, nuclear radiation protection, can solve the inability to ensure neutron shielding performance, increase the difficulty of composite plate preparation, poor processing performance and plasticity, etc. problems, achieve excellent neutron absorption performance, reduce preparation difficulty, and achieve high density

Active Publication Date: 2018-10-02
MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] The purpose of the invention of the present invention is to: aim at following the B in aluminum-based boron carbide 4 With the increase of C particle content, the preparation difficulty of the composite plate also increases, the processing performance and plasticity become poor, and it is difficult to roll, while the B in aluminum-based boron carbide 4 The content of C is too low, and the neutron shielding performance cannot be ensured, and it is difficult to ensure critical safety. An Al-B4C-B neutron absorbing material and its preparation method are provided.

Method used

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  • A kind of al-b4c-b neutron absorbing material and preparation method thereof
  • A kind of al-b4c-b neutron absorbing material and preparation method thereof
  • A kind of al-b4c-b neutron absorbing material and preparation method thereof

Examples

Experimental program
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Effect test

Embodiment 1

[0054] Step 1 Weighing: Weigh 20% of B by mass fraction 4 C powder, 0.5% B powder, 79.5% 5083 aluminum alloy powder.

[0055] Step 2 Ball milling and mixing: Mix the powders obtained in Step 1 together, use a planetary ball mill for mixing, add analytical pure alcohol until the surface of the mixed powder is submerged, the speed is 180r / min, and the ball milling time is 6 hours to obtain a mixed powder body; put the mixed powder into a constant temperature drying oven at 70°C to keep warm and dry for 30 hours to obtain a dry mixed powder.

[0056] Step 3 Cold isostatic pressing: put the dry powder obtained in step 2 into the mold, vacuumize to maintain the vacuum degree at about 8Pa, and then carry out cold isostatic pressing under the condition of 180MPa and holding pressure for 10 minutes to form a billet Body, green body density is 83%.

[0057] Step 4 Packing and high-temperature degassing: remove the mold from the body obtained in step 3, and weld it with an iron plate ...

Embodiment 2

[0060] The present embodiment is different from Example 1 in that: take 20% B by mass fraction 4 C powder, 1.0% B powder, 79.0% 5083 aluminum alloy powder. Others are the same as in Example 1.

Embodiment 3

[0062] The present embodiment is different from Example 1 in that: take 20% B by mass fraction 4 C powder, 1.5% B powder, 78.5% 5083 aluminum alloy powder. Others are the same as in Example 1.

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Abstract

The invention discloses a novel AlB4CB neutron absorbing material and a preparation method thereof. The invention aims to solve the problems that along with the content increase of B4C particles in aluminum-base boron carbide, the preparation difficulty of a composite board with aluminum-base boron carbide is also increased, the processing performance and the plasticity become bad, and rolling is difficult; if the content of B4C in aluminum-base boron carbide is too low, the neutron shielding performance cannot be ensured, and the critical safety is difficultly ensured. The composite material of which the particles are uniformly dispersed obtained by the invention has a good comprehensive performance and good resistance to radiation, has high critical safety when being used as a spent fuel storage grid material, and meets the need of neutron absorption.

Description

technical field [0001] The invention relates to the field of nuclear radiation protection, in particular to the field of neutron absorbing materials for radiation protection, in particular to an Al-B4C-B neutron absorbing material and a preparation method thereof. Background technique [0002] In recent years, with the rapid development and full utilization of nuclear energy, a large amount of spent fuel has also been produced. These spent fuels are highly radioactive and toxic, and continuously release a large amount of gamma rays and neutrons, which may cause critical accidents and seriously endanger human health and the living environment. It is estimated that after 2020, my country will unload more than 1,000 tons of spent fuel every year. Since my country does not yet have a systematic spent fuel reprocessing capacity, the accumulated amount of spent fuel will quickly exceed the spent fuel processing capacity. In the future, my country will face a daunting task in the...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22C32/00C22C21/00C22C1/05C22C1/10B22F3/04B22F3/15
CPCB22F3/04B22F3/15C22C1/05C22C21/00C22C32/0057
Inventor 鲜亚疆庞晓轩张鹏程刘鹏闯张羽廷王鑫
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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