CN111205107A - Radiation shielding composite material and preparation method thereof - Google Patents
Radiation shielding composite material and preparation method thereof Download PDFInfo
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- CN111205107A CN111205107A CN202010044290.5A CN202010044290A CN111205107A CN 111205107 A CN111205107 A CN 111205107A CN 202010044290 A CN202010044290 A CN 202010044290A CN 111205107 A CN111205107 A CN 111205107A
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B41/00—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
- C04B41/80—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone of only ceramics
- C04B41/81—Coating or impregnation
- C04B41/85—Coating or impregnation with inorganic materials
- C04B41/86—Glazes; Cold glazes
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- C—CHEMISTRY; METALLURGY
- C03—GLASS; MINERAL OR SLAG WOOL
- C03C—CHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
- C03C1/00—Ingredients generally applicable to manufacture of glasses, glazes, or vitreous enamels
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- C—CHEMISTRY; METALLURGY
- C03—GLASS; MINERAL OR SLAG WOOL
- C03C—CHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
- C03C8/00—Enamels; Glazes; Fusion seal compositions being frit compositions having non-frit additions
- C03C8/02—Frit compositions, i.e. in a powdered or comminuted form
- C03C8/10—Frit compositions, i.e. in a powdered or comminuted form containing lead
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B41/00—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
- C04B41/45—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements
- C04B41/50—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements with inorganic materials
- C04B41/5022—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements with inorganic materials with vitreous materials
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/06—Ceramics; Glasses; Refractories
Abstract
The invention relates to a radiation shielding composite material and a preparation method thereof. The technical scheme is as follows: placing an aluminum borate porous ceramic block with porosity of 54.0-94.2 vol% and normal temperature compressive strength of 304.8-456.2 MPa in a boron nitride crucible, embedding the block with a glass shielding agent containing a radiation shielding component, placing the block in a vacuum furnace, and vacuumizing to 1.33 multiplied by 10‑2Heating to 1000-1300 ℃ below Pa, and keeping the temperature for 30-90 minutes; then, sequentially cooling to 600-800 ℃ at a speed of 15-20 ℃/min and cooling to 200-500 ℃ at a speed of 5-10 ℃/min, and preserving heat; cooling, cutting and polishing to obtain the radiation shielding composite material.The glass shielding agent containing the radiation shielding component is prepared by mixing boron oxide, bismuth oxide, phosphorus oxide, silicon oxide, lead oxide, barium oxide, lithium oxide and rare earth metal oxide, and carrying out melting, water quenching and crushing. The product prepared by the invention has high compression strength, excellent shielding performance, good water and heat corrosion resistance and excellent irradiation resistance.
Description
Technical Field
The invention belongs to the technical field of shielding materials. In particular to a radiation shielding composite material and a preparation method thereof.
Background
With the gradual exhaustion of traditional fossil fuels, the development of efficient and clean novel energy sources is always a hot issue concerned by researchers. Nuclear energy is considered as the most promising clean energy source by scientists as a focus of research due to huge energy development potential, however, nuclear safety problems accompanied in the development process are also of great concern. Nuclear energy rays generally appear in the nuclear energy industry, and after the nuclear energy rays are irradiated to a human body, the human body can generate certain irreversible biological effects, and the damage degree to the human body is in direct proportion to the radiation dose absorbed by the human body; after the nuclear energy radiation irradiates the control equipment or the bearing member, the material of the equipment or the bearing member is subjected to irradiation failure, and huge potential safety hazards are generated.
At present, the use of high-efficiency radiation shielding materials to absorb attenuated rays is the best way to ensure the safety of protection personnel and equipment. The design of the radiation shielding material is considered from two aspects: (1) how to more effectively improve the absorption capacity of the material to the rays; (2) on the premise of ensuring excellent ray absorption capacity of the material, the requirements of the environment on the mechanical property, the heat conduction property, the erosion resistance and the like of the material are met. Currently, the radiation shielding materials mainly have the following problems: large volume density, low mechanical strength, poor erosion resistance, complex preparation process and high cost. Therefore, the development of a novel process for preparing a radiation shielding material with excellent performance, low price and low production cost has become an urgent problem to be solved today.
Currently, techniques for preparing radiation shielding materials include: the patent technology of 'formula of radiation shielding lead alloy' (CN201810476206.X) discloses a radiation shielding material with a multilayer special-shaped embedded structure, which takes lead alloy as a main raw material, although the shielding performance of a ray protection material in the technology is enhanced, secondary bremsstrahlung of lead is overcome, and the plasticity and toughness of the radiation shielding material are enhanced, the radiation shielding material not only has inevitable negative effects on human bodies and the environment due to excessively high lead content, but also has high production cost; the preparation of lead-containing polyimide materials with sandwich structures of royal gem and the like and the research of radiation shielding performance [ J ] Polymer science, 2018, (4):507-, The prepared PI (Pb) composite material has good shielding effect on medium-low energy gamma rays such as 241Am (59.5keV), 238Pu (79.9, 176.7keV) and the like, but the preparation process is too complicated, the organic matter content is high, the irradiation aging resistance is poor, and the high temperature resistance is poor; in addition, a document (Wuqingwen and the like; Experimental research on preparation of radiation-proof concrete by lead-zinc tailings [ J ]. ceramic science report, 2018,39(6): 769-.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and aims to provide a preparation method of a radiation shielding composite material with low production cost and simple process, and the radiation shielding composite material prepared by the method has high compressive strength, excellent shielding performance, good water and heat corrosion resistance and excellent irradiation resistance.
In order to achieve the purpose, the technical scheme adopted by the invention comprises the following steps:
step one, cutting the aluminum borate porous ceramic with the porosity of 54.0-94.2 vol% and the normal-temperature compressive strength of 304.8-456.2 MPa into blocks which can be placed in a boron nitride crucible to obtain the aluminum borate porous ceramic blocks.
Step two, mixing 32.0-40.0 wt% of boron oxide, 28.0-37.0 wt% of bismuth oxide, 1.0-5.0 wt% of phosphorus oxide, 4.0-9.0 wt% of silicon oxide, 3.0-8.0 wt% of lead oxide, 2.0-7.0 wt% of barium oxide, 4.0-8.0 wt% of lithium oxide and 2.0-5.0 wt% of rare earth metal oxide to obtain a mixture; and melting the mixture at 1400-1600 ℃, then performing water quenching on the molten glass, and crushing the molten glass until the particle size is less than 0.147mm to obtain the glass shielding agent containing the radiation shielding component.
Thirdly, placing the aluminum borate porous ceramic block in a boron nitride crucible, and embedding the aluminum borate porous ceramic block by using the glass shielding agent containing the radiation shielding component; placing the boron nitride crucible in a vacuum furnace, and vacuumizing to 1.33 multiplied by 10- 2Heating to 1000-1300 ℃ below Pa, and keeping the temperature for 30-90 minutes; then sequentially cooling to 600-800 ℃ at a speed of 15-20 ℃/min and cooling to 200-500 ℃ at a speed of 5-10 ℃/min under the condition of normal pressure, and preserving heat for 60-180 minutes; cooling, cutting and polishing to obtain the radiation shielding composite material.
In the invention: the boron oxide is analytically pure; the bismuth oxide is analytically pure; the phosphorus oxide is analytically pure; the silicon oxide is analytically pure; the lead oxide is analytically pure; the barium oxide is analytically pure; the lithium oxide is analytically pure; the rare earth metal oxide is analytically pure.
Due to the adoption of the technical scheme, compared with the prior art, the invention has the following positive effects:
1. compared with the radiation shielding material with a multilayer special-shaped embedded structure, which takes the lead alloy as a main raw material, the radiation shielding composite material prepared by the invention has low production cost. Different from the preparation method of the lead-containing polyimide radiation shielding material with the sandwich structure, the method does not need the processes of polycondensation and layer-by-layer pouring, and has simple process.
2. The aluminum borate porous ceramic block adopted by the invention has high compressive strength, and can be used as a matrix of the radiation shielding composite material, so that the radiation shielding composite material has high compressive strength.
3. According to the invention, the glass shielding agent containing the radiation shielding component is prepared by taking boron oxide, bismuth oxide, phosphorus oxide, silicon oxide, lead oxide, barium oxide, lithium oxide and rare earth metal oxide as raw materials, so that the synergistic protection effect of different elements on rays can be fully utilized, the integral ray absorption cross section of the radiation shielding composite material is improved, and the shielding performance is excellent; boron in the aluminum borate porous ceramic block also has an absorption effect on neutron rays, and the shielding performance can be improved.
4. The invention takes an aluminum borate porous ceramic block as a substrate, the porosity of the aluminum borate porous ceramic block is 54.0-94.2 vol%, and the normal-temperature compressive strength is 304.8-456.2 MPa; and (2) infiltrating the molten glass into the pores of the aluminum borate porous ceramic block by a melting infiltration method, and detecting the prepared radiation shielding composite material: the bulk density is 4.52-5.98 g/cm3The normal-temperature compressive strength is 233.7-376.5 MPa; irradiating a radiation shielding composite material (with the thickness of 2cm) by adopting an Am-Be neutron ray source and a Co60 gamma ray source, wherein the penetration rate of neutrons and gamma rays is 1.0-9.7%; the radiation shielding composite material is placed in a hydrothermal kettle and is irradiated for 15 days at 180 ℃, the mass loss rate is 1.2-4.0%, and the strength loss rate is 1.2-7.5%.
Therefore, the invention has the characteristics of low production cost and simple process, and the prepared radiation shielding composite material has high compressive strength, excellent shielding performance, good resistance to hot corrosion and excellent radiation resistance.
Detailed Description
The invention is further described with reference to specific embodiments, which do not limit the scope of the invention.
A radiation shielding composite material and a preparation method thereof. The preparation method comprises the following steps:
step one, cutting the aluminum borate porous ceramic with the porosity of 54.0-94.2 vol% and the normal-temperature compressive strength of 304.8-456.2 MPa into blocks which can be placed in a boron nitride crucible to obtain the aluminum borate porous ceramic blocks.
Step two, mixing 32.0-40.0 wt% of boron oxide, 28.0-37.0 wt% of bismuth oxide, 1.0-5.0 wt% of phosphorus oxide, 4.0-9.0 wt% of silicon oxide, 3.0-8.0 wt% of lead oxide, 2.0-7.0 wt% of barium oxide, 4.0-8.0 wt% of lithium oxide and 2.0-5.0 wt% of rare earth metal oxide to obtain a mixture; and melting the mixture at 1400-1600 ℃, then performing water quenching on the molten glass, and crushing the molten glass until the particle size is less than 0.147mm to obtain the glass shielding agent containing the radiation shielding component.
Thirdly, placing the aluminum borate porous ceramic block in a boron nitride crucible, and embedding the aluminum borate porous ceramic block by using the glass shielding agent containing the radiation shielding component; placing the boron nitride crucible in a vacuum furnace, and vacuumizing to 1.33 multiplied by 10- 2Heating to 1000-1300 ℃ below Pa, and keeping the temperature for 30-90 minutes; then sequentially cooling to 600-800 ℃ at a speed of 15-20 ℃/min and cooling to 200-500 ℃ at a speed of 5-10 ℃/min under the condition of normal pressure, and preserving heat for 60-180 minutes; cooling, cutting and polishing to obtain the radiation shielding composite material.
In this embodiment: the boron oxide is analytically pure; the bismuth oxide is analytically pure; the phosphorus oxide is analytically pure; the silicon oxide is analytically pure; the lead oxide is analytically pure; the barium oxide is analytically pure; the lithium oxide is analytically pure; the rare earth metal oxide is analytically pure. The detailed description is omitted in the embodiments.
Example 1
A radiation shielding composite material and a preparation method thereof. The preparation method comprises the following steps:
step one, cutting the aluminum borate porous ceramic with the porosity of 82.5 vol% and the normal-temperature compressive strength of 335.3MPa into blocks which can be placed in a boron nitride crucible to obtain the aluminum borate porous ceramic blocks.
Step two, mixing 34.0 wt% of boron oxide, 33.0 wt% of bismuth oxide, 5.0 wt% of phosphorus oxide, 9.0 wt% of silicon oxide, 3.0 wt% of lead oxide, 4.0 wt% of barium oxide, 8.0 wt% of lithium oxide and 4.0 wt% of rare earth metal oxide to obtain a mixture; and melting the mixture at 1400 ℃, then performing water quenching on the molten glass, and crushing the molten glass until the particle size is less than 0.147mm to obtain the glass shielding agent containing the radiation shielding component.
Thirdly, placing the aluminum borate porous ceramic block in a boron nitride crucible, and embedding the aluminum borate porous ceramic block by using the glass shielding agent containing the radiation shielding component; placing the boron nitride crucible in a vacuum furnace, and vacuumizing to 1.33 multiplied by 10- 2Pa, heating to 1000 ℃, and keeping the temperature for 90 minutes; then, under the condition of normal pressure, the temperature is reduced to 750 ℃ at the speed of 16 ℃/min and to 400 ℃ at the speed of 8 ℃/min in sequence, and the temperature is preserved for 140 minutes; cooling, cutting and polishing to obtain the radiation shielding composite material.
The radiation shielding composite material prepared in the embodiment is detected as follows: the bulk density is 4.94g/cm3The normal-temperature compressive strength is 269.2 MPa; an Am-Be neutron ray source and a Co60 gamma ray source are adopted to irradiate a radiation shielding composite material (with the thickness of 2cm), and the penetration rate of neutrons and gamma rays is 7.8%; the radiation shielding composite material is placed in a hydrothermal kettle and is irradiated for 15 days at 180 ℃, the mass loss rate is 4.0 percent, and the strength loss rate is 2.8 percent.
Example 2
A radiation shielding composite material and a preparation method thereof. The preparation method comprises the following steps:
step one, cutting the aluminum borate porous ceramic with the porosity of 71.4 vol% and the normal-temperature compressive strength of 369.5MPa into blocks which can be placed in a boron nitride crucible to obtain the aluminum borate porous ceramic blocks.
Step two, mixing 40.0 wt% of boron oxide, 30.0 wt% of bismuth oxide, 3.0 wt% of phosphorus oxide, 7.0 wt% of silicon oxide, 6.0 wt% of lead oxide, 7.0 wt% of barium oxide, 4.0 wt% of lithium oxide and 3.0 wt% of rare earth metal oxide to obtain a mixture; and melting the mixture at 1450 ℃, then performing water quenching on the molten glass, and crushing the molten glass until the particle size is less than 0.147mm to obtain the glass shielding agent containing the radiation shielding component.
Thirdly, placing the aluminum borate porous ceramic block in a boron nitride crucible, and embedding the aluminum borate porous ceramic block by using the glass shielding agent containing the radiation shielding component; placing the boron nitride crucible in a vacuum furnace, and vacuumizing to 1.32 multiplied by 10- 2Pa, heating to 1050 ℃, and keeping the temperature for 30 minutes; then, under the condition of normal pressure, the temperature is reduced to 700 ℃ at the speed of 17 ℃/min and to 350 ℃ at the speed of 6 ℃/min in sequence, and the temperature is preserved for 120 minutes; cooling, cutting and polishing to obtain the radiation shielding composite material.
The radiation shielding composite material prepared in the embodiment is detected as follows: the bulk density is 5.26g/cm3The normal-temperature compressive strength is 302.1 MPa; an Am-Be neutron ray source and a Co60 gamma ray source are adopted to irradiate a radiation shielding composite material (with the thickness of 2cm), and the penetration rate of neutrons and gamma rays is 5.5%; the radiation shielding composite material is placed in a hydrothermal kettle and is irradiated for 15 days at 180 ℃, the mass loss rate is 3.4 percent, and the strength loss rate is 4.4 percent.
Example 3
A radiation shielding composite material and a preparation method thereof. The preparation method comprises the following steps:
step one, cutting the aluminum borate porous ceramic with the porosity of 54.0 vol% and the normal-temperature compressive strength of 456.2MPa into blocks which can be placed in a boron nitride crucible to obtain the aluminum borate porous ceramic blocks.
Step two, mixing 32.0 wt% of boron oxide, 37.0 wt% of bismuth oxide, 1.0 wt% of phosphorus oxide, 6.0 wt% of silicon oxide, 8.0 wt% of lead oxide, 7.0 wt% of barium oxide, 4.0 wt% of lithium oxide and 5.0 wt% of rare earth metal oxide to obtain a mixture; and melting the mixture at 1600 ℃, then performing water quenching on the molten glass, and crushing the molten glass until the particle size is less than 0.147mm to obtain the glass shielding agent containing the radiation shielding component.
Thirdly, placing the aluminum borate porous ceramic block in a boron nitride crucible, and using the glass containing the radiation shielding componentEmbedding the aluminum borate porous ceramic block by the glass shielding agent; placing the boron nitride crucible in a vacuum furnace, and vacuumizing to 1.31 multiplied by 10- 2Pa, heating to 1200 ℃, and keeping the temperature for 60 minutes; then, under the condition of normal pressure, the temperature is reduced to 650 ℃ at the speed of 18 ℃/min and to 250 ℃ at the speed of 7 ℃/min in sequence, and the temperature is preserved for 100 minutes; cooling, cutting and polishing to obtain the radiation shielding composite material.
The radiation shielding composite material prepared in the embodiment is detected as follows: the bulk density is 5.98g/cm3The normal-temperature compressive strength is 376.5 MPa; an Am-Be neutron ray source and a Co60 gamma ray source are adopted to irradiate a radiation shielding composite material (with the thickness of 2cm), and the penetration rate of neutrons and gamma rays is 1.0%; the radiation shielding composite material is placed in a hydrothermal kettle and is irradiated for 15 days at 180 ℃, the mass loss rate is 2.1 percent, and the strength loss rate is 7.5 percent.
Example 4
A radiation shielding composite material and a preparation method thereof. The preparation method comprises the following steps:
step one, cutting the aluminum borate porous ceramic with the porosity of 65.3 vol% and the normal-temperature compressive strength of 408.7MPa into blocks which can be placed in a boron nitride crucible to obtain the aluminum borate porous ceramic blocks.
Step two, mixing 37.0 wt% of boron oxide, 36.0 wt% of bismuth oxide, 4.0 wt% of phosphorus oxide, 4.0 wt% of silicon oxide, 6.0 wt% of lead oxide, 6.0 wt% of barium oxide, 5.0 wt% of lithium oxide and 2.0 wt% of rare earth metal oxide to obtain a mixture; and melting the mixture at 1550 ℃, then performing water quenching on the molten glass, and crushing the molten glass until the particle size is less than 0.147mm to obtain the glass shielding agent containing the radiation shielding component.
Thirdly, placing the aluminum borate porous ceramic block in a boron nitride crucible, and embedding the aluminum borate porous ceramic block by using the glass shielding agent containing the radiation shielding component; placing the boron nitride crucible in a vacuum furnace, and vacuumizing to 1.30 multiplied by 10- 2Pa, heating to 1300 ℃, and keeping the temperature for 50 minutes; then sequentially cooling to 600 ℃ at the speed of 20 ℃/min and 200 ℃ at the speed of 10 ℃/min under the condition of normal pressure, and preserving heat for 180 minutes; the mixture is cooled down and then is cooled down,and cutting and polishing to obtain the radiation shielding composite material.
The radiation shielding composite material prepared in the embodiment is detected as follows: the bulk density is 5.63g/cm3The normal temperature compressive strength is 341.6 MPa; an Am-Be neutron ray source and a Co60 gamma ray source are adopted to irradiate a radiation shielding composite material (with the thickness of 2cm), and the penetration rate of neutrons and gamma rays is 3.9%; the radiation shielding composite material is placed in a hydrothermal kettle and is irradiated for 15 days at 180 ℃, the mass loss rate is 1.2 percent, and the strength loss rate is 5.9 percent.
Example 5
A radiation shielding composite material and a preparation method thereof. The preparation method comprises the following steps:
step one, cutting the aluminum borate porous ceramic with the porosity of 94.2 vol% and the normal-temperature compressive strength of 304.8MPa into blocks which can be placed in a boron nitride crucible to obtain the aluminum borate porous ceramic blocks.
Step two, mixing 35.0 wt% of boron oxide, 28.0 wt% of bismuth oxide, 5.0 wt% of phosphorus oxide, 9.0 wt% of silicon oxide, 8.0 wt% of lead oxide, 2.0 wt% of barium oxide, 8.0 wt% of lithium oxide and 5.0 wt% of rare earth metal oxide to obtain a mixture; and melting the mixture at 1500 ℃, then performing water quenching on the molten glass, and crushing the molten glass until the particle size is less than 0.147mm to obtain the glass shielding agent containing the radiation shielding component.
Thirdly, placing the aluminum borate porous ceramic block in a boron nitride crucible, and embedding the aluminum borate porous ceramic block by using the glass shielding agent containing the radiation shielding component; placing the boron nitride crucible in a vacuum furnace, and vacuumizing to 1.25 multiplied by 10- 2Pa, heating to 1150 ℃, and keeping the temperature for 75 minutes; then, under the condition of normal pressure, the temperature is reduced to 800 ℃ at the speed of 15 ℃/min and to 500 ℃ at the speed of 5 ℃/min in sequence, and the temperature is preserved for 60 minutes; cooling, cutting and polishing to obtain the radiation shielding composite material.
The radiation shielding composite material prepared in the embodiment is detected as follows: the bulk density is 4.52g/cm3The normal-temperature compressive strength is 233.7 MPa; radiation shielding composite material (thickness 2 c) adopting Am-Be neutron ray source and Co60 gamma ray sourcem) irradiating, wherein the penetration rate of neutrons and gamma rays is 9.7%; the radiation shielding composite material is placed in a hydrothermal kettle and is irradiated for 15 days at 180 ℃, the mass loss rate is 2.9 percent, and the strength loss rate is 1.2 percent.
Compared with the prior art, the specific implementation mode has the following positive effects:
1. compared with the radiation shielding material with the multilayer special-shaped embedding structure, which takes the lead alloy as the main raw material, the radiation shielding composite material prepared by the embodiment has low production cost. Different from the preparation method of the lead-containing polyimide radiation shielding material with the sandwich structure, the method does not need the processes of polycondensation and layer-by-layer pouring, and has simple process.
2. The aluminum borate porous ceramic block adopted by the embodiment has high compressive strength, and can be used as a matrix of the radiation shielding composite material, so that the radiation shielding composite material has high compressive strength.
3. According to the specific embodiment, the glass shielding agent containing the radiation shielding component is prepared by taking boron oxide, bismuth oxide, phosphorus oxide, silicon oxide, lead oxide, barium oxide, lithium oxide and rare earth metal oxide as raw materials, so that the synergistic protection effect of different elements on rays can be fully utilized, the integral ray absorption cross section of the radiation shielding composite material is improved, and the shielding performance is excellent; boron in the aluminum borate porous ceramic block also has an absorption effect on neutron rays, and the shielding performance can be improved.
4. The specific embodiment takes the aluminum borate porous ceramic block as a substrate, the porosity of the aluminum borate porous ceramic block is 54.0-94.2 vol%, and the normal-temperature compressive strength is 304.8-456.2 MPa; and (2) infiltrating the molten glass into the pores of the aluminum borate porous ceramic block by a melting infiltration method, and detecting the prepared radiation shielding composite material: the bulk density is 4.52-5.98 g/cm3The normal-temperature compressive strength is 233.7-376.5 MPa; irradiating a radiation shielding composite material (with the thickness of 2cm) by adopting an Am-Be neutron ray source and a Co60 gamma ray source, wherein the penetration rate of neutrons and gamma rays is 1.0-9.7%; the radiation shielding composite material is placed in a hydrothermal kettle and is irradiated for 15 days at 180 ℃, the mass loss rate is 1.2-4.0%, and the strength loss rate is 1.2-7.5%.
Therefore, the specific embodiment has the characteristics of low production cost and simple process, and the prepared radiation shielding composite material has high compressive strength, excellent shielding performance, good water and heat corrosion resistance and excellent irradiation resistance.
Claims (10)
1. A preparation method of a radiation shielding composite material is characterized by comprising the following steps:
step one, cutting the aluminum borate porous ceramic with the porosity of 54.0-94.2 vol% and the normal-temperature compressive strength of 304.8-456.2 MPa into blocks which can be placed in a boron nitride crucible to obtain aluminum borate porous ceramic blocks;
step two, mixing 32.0-40.0 wt% of boron oxide, 28.0-37.0 wt% of bismuth oxide, 1.0-5.0 wt% of phosphorus oxide, 4.0-9.0 wt% of silicon oxide, 3.0-8.0 wt% of lead oxide, 2.0-7.0 wt% of barium oxide, 4.0-8.0 wt% of lithium oxide and 2.0-5.0 wt% of rare earth metal oxide to obtain a mixture; melting the mixture at 1400-1600 ℃, then performing water quenching on the molten glass, and crushing the molten glass until the particle size is less than 0.147mm to obtain a glass shielding agent containing radiation shielding components;
thirdly, placing the aluminum borate porous ceramic block in a boron nitride crucible, and embedding the aluminum borate porous ceramic block by using the glass shielding agent containing the radiation shielding component; placing the boron nitride crucible in a vacuum furnace, and vacuumizing to 1.33 multiplied by 10-2Heating to 1000-1300 ℃ below Pa, and keeping the temperature for 30-90 minutes; then sequentially cooling to 600-800 ℃ at a speed of 15-20 ℃/min and cooling to 200-500 ℃ at a speed of 5-10 ℃/min under the condition of normal pressure, and preserving heat for 60-180 minutes; cooling, cutting and polishing to obtain the radiation shielding composite material.
2. The method of claim 1, wherein the boron oxide is analytically pure.
3. The method of claim 1, wherein the bismuth oxide is analytically pure.
4. The method of claim 1, wherein the phosphorus oxide is analytically pure.
5. The method of claim 1, wherein the silica is analytically pure.
6. The method of claim 1, wherein the lead oxide is analytically pure.
7. The method of claim 1, wherein the barium oxide is analytically pure.
8. The method of claim 1, wherein the lithium oxide is analytically pure.
9. The method of claim 1, wherein the rare earth metal oxide is analytically pure.
10. A radiation shielding composite material, characterized in that the radiation shielding composite material is a radiation shielding composite material produced by the method for producing a radiation shielding composite material according to any one of claims 1 to 9.
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113185278A (en) * | 2021-04-22 | 2021-07-30 | 武汉科技大学 | Bismuth borate ceramic material and preparation method thereof |
| CN116161945A (en) * | 2022-12-23 | 2023-05-26 | 河北领标科技发展有限公司 | Nuclear radiation resistant ceramic large plate and preparation method and application thereof |
| CN116655241A (en) * | 2023-04-23 | 2023-08-29 | 西北核技术研究所 | High-temperature-resistant high-boron glass sand neutron absorption material and preparation method thereof |
| CN116655241B (en) * | 2023-04-23 | 2024-04-26 | 西北核技术研究所 | High-temperature-resistant high-boron glass sand neutron absorption material and preparation method thereof |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113185278A (en) * | 2021-04-22 | 2021-07-30 | 武汉科技大学 | Bismuth borate ceramic material and preparation method thereof |
| CN113185278B (en) * | 2021-04-22 | 2023-02-03 | 武汉科技大学 | Bismuth borate ceramic material and preparation method thereof |
| CN116161945A (en) * | 2022-12-23 | 2023-05-26 | 河北领标科技发展有限公司 | Nuclear radiation resistant ceramic large plate and preparation method and application thereof |
| CN116655241A (en) * | 2023-04-23 | 2023-08-29 | 西北核技术研究所 | High-temperature-resistant high-boron glass sand neutron absorption material and preparation method thereof |
| CN116655241B (en) * | 2023-04-23 | 2024-04-26 | 西北核技术研究所 | High-temperature-resistant high-boron glass sand neutron absorption material and preparation method thereof |
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