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A manufacturing method of boron-aluminum neutron-absorbing shielding cylinder for spent fuel storage and transportation container

A shielding cylinder and spent fuel technology, applied in the field of nuclear material manufacturing technology, can solve the problems that the manufacturing method cannot be found and the structural form has not been reported, and achieve the effect of large arc adjustment, wide application and diversified forms

Active Publication Date: 2021-08-17
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The United States was the first to develop and apply boron-aluminum materials, but its structural form has not been reported in spent fuel storage containers, and the manufacturing method cannot be found

Method used

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  • A manufacturing method of boron-aluminum neutron-absorbing shielding cylinder for spent fuel storage and transportation container
  • A manufacturing method of boron-aluminum neutron-absorbing shielding cylinder for spent fuel storage and transportation container

Examples

Experimental program
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Effect test

Embodiment 1

[0024] Single-layer shielding bobbin unit structure: 2mm thick B 4 Boron-aluminum arc plates with a C content of 31%, two arc plates with a diameter of 200mm and a height of 120mm, and the clips are H-shaped boron-aluminum materials with a thickness of 5mm and a length of 120mm. The curved rolling tool makes the H-shaped clip fasten the two arc plates.

[0025] Three-layer shielding bobbin unit structure: 2mm thick B 4 Boron-aluminum arc plates with a C content of 31%. The diameters of the arc plates are 450mm, 454mm, and 458mm, and the heights are 200mm. Three pieces are assembled to form a multi-layer shielding tube. The schematic diagram of its structure is shown in figure 2 .

Embodiment 2

[0027] Manufacture of single-layer shielding tube arc plate: 2mm thick B 4 For boron-aluminum plates with a C content of 31%, cut out two rectangular plates of 314mm×120mm, put them in a heating furnace at 300°C to 550°C, and hold the heat for ≥5 minutes; send the plate in a hot state into the plate rolling machine, The curved plate is rolled according to the radian of the preset coil diameter of 200mm, and then the made curved plate is placed in a finishing steel mold at 300°C to 550°C for finishing, and the finishing time is ≥5min; after finishing, it is cut and cut. Open the finishing mold and take out the boron aluminum arc plate. The two arc plates are butted and assembled into a single-layer shielded cartridge unit.

[0028] Three-layer shielding cylinder arc plate manufacturing: 2mm thick B 4 For boron-aluminum plates with a C content of 31%, cut out 3 rectangular plates of 500mm×200mm, put them in a heating furnace at 300°C to 550°C, and hold the heat for ≥5 minutes;...

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Abstract

The invention belongs to the technical field of nuclear material manufacturing technology, and in particular relates to a manufacturing method of a boron-aluminum neutron-absorbing shielding cylinder used for spent fuel storage and transportation containers. Specifically, the method includes the following steps: step 1, structural design of the boron-aluminum shielding cylinder; step 2, preparation of the boron-aluminum arc plate; and step 3, assembly of the boron-aluminum shielding cylinder. The difficult-to-bend boron-aluminum plate is made into a cylindrical structure with adjustable diameter. The total amount of boron loaded in the product can be adjusted according to the design requirements, which can realize radial full shielding. The circular area is small and space-saving. The material itself has good thermal conductivity and is suitable for Dry storage.

Description

technical field [0001] The invention belongs to the technical field of nuclear material manufacturing technology, and in particular relates to a manufacturing method of a boron-aluminum neutron-absorbing shielding cylinder used for spent fuel storage and transportation containers. Background technique [0002] After attenuation and heat release, spent fuel used in nuclear reactors is packed into spent fuel storage containers and transported to reprocessing plants for processing or deep buried dry storage. Therefore, it is still necessary to use neutron absorbing material as a shielding layer in the storage and transportation container to absorb the remaining neutrons of spent fuel. There are many neutron-absorbing materials, such as materials containing cadmium, gadolinium, samarium, and boron; cadmium has a large neutron absorption cross-section and has a good neutron absorption effect, but it is highly toxic and pollutes the environment; gadolinium, samarium The neutron a...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B21D5/00B21D39/00B21C37/00
CPCB21C37/00B21D5/00B21D39/00
Inventor 孙长龙黄健民
Owner NUCLEAR POWER INSTITUTE OF CHINA