Neutron deceleration composite material

A technology of composite materials and mixed materials, applied in the direction of X-ray/γ-ray/particle irradiation therapy, etc., can solve the problems of poor economic performance, high radioactivity, unfriendly environment, etc., achieve good absorption effect, obvious advantages, and beneficial to China The effect of sub-deceleration

Pending Publication Date: 2022-01-07
CHINA SPALLATION NEUTRON SOURCE SCI CENT +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0011] The object of the present invention is to solve the problems existing in the prior art, and provide a neutron deceleration composite material to overcome the problems of poor economic performance, high radioactivity induced by neutron irradiation for a long time, and unfriendly environment. It has excellent neutron deceleration performance, can decelerate fast neutrons to the epithermal neutron energy region, and is suitable for the field of boron neutron capture therapy

Method used

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Examples

Experimental program
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Effect test

Embodiment 1

[0040] A kind of neutron deceleration composite material, by weight percentage, including Al (wt%): 28.0, MgF 2 (wt%): 1.0, AlF 3 (wt%): 69.0, 6 The mixed material of LiF (wt%): 1.0 and Cu (wt%): 1.0, through the powder sintering process of the powder sintering equipment, the moderator block is formed by powder or powder crushing.

[0041] Among the above materials, nuclides such as aluminum, fluorine, and magnesium have small neutron (n, γ) absorption cross-sections and large elastic scattering cross-sections in the superthermal energy region, which is conducive to moderating fast neutrons to the superthermal energy region; natural lithium is divided into 6 Li and 7 Two kinds of nuclides, Li, have smaller atomic numbers and have good slowing or decelerating ability, and at the same time 6 Li has a large neutron absorption cross-section in the hot zone and the lower energy zone, which can absorb thermal neutrons, which is convenient for beam shaping in boron neutron capture...

Embodiment 2

[0043] This embodiment provides a kind of neutron deceleration composite material, by weight percentage, including Al (wt%): 28.5, MgF 2 (wt%): 2.0, AlF 3 (wt%): 66.0, 6 LiF (wt%): 1.0, Cu (wt%): 0.5, Mg (wt%): 2.0 mixed materials, through powder sintering equipment through powder sintering process, the moderator block is formed by powder or powder crushing.

[0044] All the other are the same as in Example 1.

[0045]It can be seen that the addition of pure magnesium powder in this embodiment can still slow down fast neutrons to the epithermal energy region, and achieve the purpose of small neutron (n, γ) absorption cross section and large elastic scattering cross section in the superthermal energy region.

Embodiment 3

[0047] This embodiment provides a neutron deceleration composite material, in terms of weight percentage, compared with Embodiment 1, the difference is that it includes Al (wt%): 28.0, Mg (wt%): 1.0, AlF 3 (wt%): 69.0, 6 LiF (wt%): 1.0, Cu (wt%): 1.0;

[0048] All the other are the same as in Example 1.

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Abstract

The invention discloses a neutron deceleration composite material. The neutron deceleration composite material comprises a mixed material, a material which accounts for 0.1-5% of the weight of the mixed material and contains a 6Li element, and Cu which accounts for 0.1-5% of the weight of the mixed material, and the mixed material comprises one or a mixture of more of Al, MgF2 and AlF3; the mixed material comprises the following components in percentage by mass: 10-95% of pure aluminum powder, 20%-80% of aluminum fluoride powder, 0.1%-15% of magnesium fluoride powder; the material containing the < 6 > Li element is < 6 > LiF powder; the mixed material further comprises pure magnesium powder, and the mass percent of the pure magnesium powder is 0.1-5%. The radioactivity of the material can be attenuated to an exemption level or below within a short time when the material is decommissioned at the last stage of the device or equipment, and the neutron deceleration composite material has obvious advantages in the aspects of radioactive waste disposal method and economy.

Description

technical field [0001] The invention relates to the technical field of metal matrix composite materials, in particular to a neutron deceleration composite material used for BNCT boron neutron capture therapy equipment to obtain neutron beams of a specific energy range. Background technique [0002] The neutron energy spectrum produced by various radiation sources such as reactor neutron sources, accelerator neutron generators and isotope neutron sources in China is basically a continuous energy spectrum in which fast neutron components are absolutely dominant, and is widely used in national defense and nuclear power and nuclear medicine. In the field of boron neutron capture therapy (BNCT) treatment, neutron beams with specific energy segments are required for treatment, such as thermal neutrons (En<0.5eV) for surface cancer treatment, epithermal neutrons (0.5eV≤En≤10KeV) ) has high energy, can penetrate human tissue at a certain depth, and is used for the treatment of d...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C29/00A61N5/10C22C1/05
CPCC22C29/00C22C1/05A61N5/10A61N2005/109
Inventor 胡志良梁天骄傅世年
Owner CHINA SPALLATION NEUTRON SOURCE SCI CENT
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