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a high b 4 High-efficiency preparation method of c-content aluminum-based neutron-absorbing material sheet

An absorbing material and high-efficiency technology, which is applied in the field of preparation of aluminum-based neutron absorbing materials for spent fuel storage. Plastic deformation ability and the effect of improving the amount of rolling deformation

Active Publication Date: 2019-08-09
中科复材(滨州)新材料有限公司
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] The object of the present invention is to provide high B 4 A high-efficiency preparation method for aluminum-based neutron-absorbing material plates with C content, solving the problem of preparing high B in existing methods 4 C content aluminum-based neutron absorbing material ingot is difficult, the extrusion die wears high during the extrusion process, it is easy to crack and the rolling efficiency is low, and it is suitable for the preparation of high-efficiency neutron absorbing materials for wet storage and transportation of spent fuel.

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0021] 40wt%B 4 C-6061 aluminum alloy mixed powder (B 4 C particle average size 44 microns) is packed into the steel pipe mold of diameter 380mm, and one end is sealed with 6061 aluminum alloy gaskets of 75mm thickness, and the other end is sealed with graphite paper and steel gasket, and cold-pressed to 60% compactness. Then, in a vacuum hot-pressing furnace, a billet with a density of 99.5% is hot-pressed using a process of 640°C×4h@50MPa. After the billet is taken out of the mold, the surface impurities are removed, and the thickness of the aluminum pad is kept at 70mm. Place the aluminum pad end in front of the extrusion, and extrude at 460°C to form a strip with a cross-section of 290×30mm. A layer of aluminum coating with uniform thickness is formed on the surface of the strip, and the strip has no cracks. Cut the strip into 350-500mm sections, roll to 11mm after 6-8 passes under the annealing process of 450℃×1h per pass and about 10-15% rolling deformation, and machine...

Embodiment 2

[0027] 33wt%B 4 C-6061 aluminum alloy mixed powder (B 4 C particle average size 28 microns) is packed into the steel pipe mold of diameter 450mm, and one end is sealed with 90mm thick 6061 aluminum alloy gasket, and the other end is sealed with graphite paper and steel gasket, and cold-pressed to 70% compactness. Then, in a vacuum hot-pressing furnace, a billet with a density of 99.8% is hot-pressed using a process of 620°C×4h@50MPa. After the billet is taken out of the mold, the surface impurities are removed, and the thickness of the aluminum pad is kept at 80mm. Place the aluminum pad end in front of the extrusion, and extrude at 460°C to form a strip with a cross-section of 290×30mm. A layer of aluminum coating with uniform thickness is formed on the surface of the strip, and the strip has no cracks. Cut the strip into 350-500mm sections, roll to 10mm after 5-6 passes under the annealing process of 450℃×1h per pass and about 15-20% rolling deformation, and machine the alu...

Embodiment 3

[0033] 21wt%B 4 C-6061 aluminum alloy mixed powder (B 4 C particle average size 3.5 micron) is packed in the steel pipe mold of diameter 380mm, and one end is sealed with 40mm thick aluminum pad, and the other end is sealed with graphite paper and steel pad, and cold-pressed to 75% compactness. Then, in a vacuum hot-pressing furnace, a billet with a density of 99.9% is hot-pressed using a process of 580°C×4h@70MPa. After the billet is taken out of the mold, the surface impurities are removed, and the thickness of the aluminum pad is kept at 35mm. Place the aluminum pad end in front of the extrusion, and extrude at 420°C to form a strip with a cross-section of 290×30mm. A layer of aluminum coating with uniform thickness is formed on the surface of the strip without cracking. The strip is cut into 350-500mm sections, rolled to 2.3mm by 7-8 passes under the annealing process of 420℃×1h per pass and about 20-30% rolling deformation, and the final sandwich structure finished plate...

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Abstract

The invention relates to a high-efficiency preparation method of a high-B4C-content and aluminum-based neutron absorption material sheet material applied to storage and transportation of spent fuel. The high-efficiency preparation method comprises the following steps: (1) sealing the lower end of a steel pipe mold by utilizing a pure aluminum or aluminum alloy cushion; (2) filling the steel pipe mold with boron carbide-aluminum or aluminum alloy mixed powder; sealing the upper end of the steel pipe mold and cold-pressing; (3) putting the sealed steel pipe mold into a vacuum hot pressing furnace, and hotly pressing and sintering to prepare a dense blank ingot; (4) hot-extruding the blank ingot with the aluminum or aluminum alloy cushion into a strip plate, wherein in an extruding process, the aluminum or aluminum alloy cushion is arranged at a front part, and the surface of the extruded strip plate is covered with one aluminum clad layer; (5) cutting the extruded strip plate with the aluminum clad layer into needed sizes, and repeatedly annealing and hot-rolling; after rolling the sheet material into certain thickness, removing the aluminum clad layers on upper and lower surfaces (or not removing); repeatedly annealing and hot-rolling to obtain the finished B4C / Al neutron absorption material sheet material. With the adoption of the method provided by the invention, the high-B4C-content and aluminum-based neutron absorption material sheet material can be rolled under relatively high efficiency.

Description

technical field [0001] The invention belongs to the field of preparation of aluminum-based neutron absorbing materials for spent fuel storage and specifically provides a high B 4 A high-efficiency preparation method for aluminum-based neutron-absorbing material plates with C content. The material can be used in the manufacture of spent fuel dry storage, grids for transport containers and other fields. Background technique [0002] The nuclear fuel used in nuclear power plants is generally called spent fuel. According to statistics, a one-million-kilowatt nuclear power unit discharges about 20 tons of spent fuel every year. Due to the difficulty and high cost of spent fuel reprocessing, most countries currently adopt temporary storage methods, which are divided into wet storage and dry storage. Generally, after the spent fuel is unloaded from the reactor, it is temporarily stored in the spent fuel storage pool for (5-15) years, and the spent fuel decays to a certain extent ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B22F3/02B22F3/14B22F3/24C22C32/00C22C21/00C22F1/04
CPCB22F3/02B22F3/14B22F3/24B22F2003/145B22F2003/248C22C21/00C22C32/0057C22F1/04
Inventor 王全兆王东肖伯律倪丁瑞马宗义
Owner 中科复材(滨州)新材料有限公司
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