CN107316667B - A kind of radiation protection material and its manufacturing method - Google Patents
A kind of radiation protection material and its manufacturing method Download PDFInfo
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- CN107316667B CN107316667B CN201710442490.4A CN201710442490A CN107316667B CN 107316667 B CN107316667 B CN 107316667B CN 201710442490 A CN201710442490 A CN 201710442490A CN 107316667 B CN107316667 B CN 107316667B
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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
- G21F1/10—Organic substances; Dispersions in organic carriers
- G21F1/103—Dispersions in organic carriers
- G21F1/106—Dispersions in organic carriers metallic dispersions
Abstract
The invention discloses a kind of radiation protection materials, count by weight percentage, including following components: tungsten: 15% ~ 40%;Antimony: 5% ~ 20%;Bismuth: 30% ~ 50%;Tin: 2% ~ 8%;Tantalum: 1% ~ 2%;Macromolecule toughness substrate: 8% ~ 20%.Beneficial effects of the present invention: radiation protection material of the present invention shield effectiveness in condition of equivalent thickness is substantially better than the non-lead protective materials being currently known, under same shield effectiveness, weight is lighter than other non-lead radiation protection materials, and there is shield effectiveness to gamma-rays, than at present in the world using E.I.Du Pont Company production most light non-lead radiation protection material it is also light by 10% or more, Unit Weight, property at high and low temperature and in terms of have a clear superiority.Meanwhile the present invention also provides a kind of manufacturing methods of radiation protection material.
Description
Technical field
The present invention relates to radiation protection technical fields, it particularly relates to a kind of radiation protection material and its manufacturing method.
Background technique
In daily life, X-ray, gamma-rays are two kinds of basic rays, and have certain danger to human body and environment
Harmful ray, traditional preventive means are control amount of radiation, reduce action time and shielded using protective materials.Since lead has
Stop the good effects of ray, so being widely used in shielding material and protective articles, but lead is heavy metal, has very strong
Toxic side effect, Long Term Contact will lead to lead poisoning, is easy to suffer from blood disease and cancer.Lead not only damages fecundity, moreover it is possible to enable
The brain and kidney of children and adults is badly damaged, and serious person can lead to death.For this purpose, many professional protection companies of Chinese and western and phase
Close the radiation protection material that research unit pays much attention to research and develop and develop non-lead or few lead.
The properties of product that foreign study mechanism researches and develops at present have certain limitation, pay no attention in the high energy spectral coverage protection effect of ray
Think, and heavier-weight, flexibility is general, is typically only capable to use at room temperature, and price is high.And domestic existing radiation protection material
Material be essentially all it is leaded, unleaded radiation protection material is very few, and the overwhelming majority leans on import, these unleaded radiation protection materials
Material can only have certain protection effect to X-ray, poor to gamma ray shielding effect.
Current non-lead radiation protection material both domestic and external is generally all labeled with it is not recommended that in the environment of having gamma-ray irradiation
It uses.Domestic and international non-lead radiation protection material generally uses two or three kind of material addition to be made such as: tungsten and antimony or antimony, bismuth, tungsten
And different components make non-lead radiation protection material, due to having many heavy metals and component ratio is high, lead to the weight of material
Heavier, flexibility is poor, can only generally use at room temperature.
For the problems in the relevant technologies, currently no effective solution has been proposed.
Summary of the invention
For above-mentioned technical problem in the related technology, the present invention proposes a kind of radiation protection material and its manufacturing method,
It is not only fine to X-ray protection effect, shielding protection can also be carried out to gamma-rays, be free of lead, compared with general non-lead material
It is light-weight, flexibility is good, use temperature range is wide, cost performance is high.
To realize the above-mentioned technical purpose, the technical scheme of the present invention is realized as follows:
A kind of radiation protection material, it is count by weight percentage, composed of the following components: tungsten: 15%~40%;Antimony: 5%
~20%;Bismuth: 30%~50%;Tin: 2%~8%;Tantalum: 1%~2%;Macromolecule toughness substrate: 8%~20%.
Further, the macromolecule toughness substrate is organic silica gel.
Further, the organic silica gel hardness range is 60~70 degree.
Further, the purity of the tungsten is greater than 98%, and the purity of the antimony is greater than 98%, and the purity of the bismuth is greater than
98%, the purity of the tin is greater than 99%, and the purity of the tantalum is greater than 95%.
Further, the tungsten is 35%;The antimony is 10%;The bismuth is 30%;The tin is 5%;The tantalum is
1%;The macromolecule toughness substrate is 19%.
Further, the tungsten is 30%;The antimony is 15%;The bismuth is 35%;The tin is 8%;The tantalum is
1%;The macromolecule toughness substrate is 11%.
Further, the tungsten is 40%;The antimony is 5%;The bismuth is 40%;The tin is 2%;The tantalum is
2%;The macromolecule toughness substrate is 11%.
Further, the tungsten is 15%;The antimony is 20%;The bismuth is 45%;The tin is 5%;The tantalum is
1%;The macromolecule toughness substrate is 14%.
According to another aspect of the present invention, a kind of manufacturing method of radiation protection material is provided, is included the following steps:
S1. prepare raw material as following weight percent:
Tungsten: 15%~40%;
Antimony: 5%~20%;
Bismuth: 30%~50%;
Tin: 2%~8%;
Tantalum: 1%~2%;
Macromolecule toughness substrate: 8%~20%;
S2. tungsten powder, antimony powder, bismuth meal are put into blender at normal temperature and are stirred evenly for use;
S3. tantalum powder and glass putty are added into macromolecule toughness substrate at normal temperature and are stirred evenly;
S4., mixed-powder obtained in step S2 is added into step S3 to the macromolecule toughness for being mixed with tantalum powder and glass putty
It is kneaded in matrix, mixing time is no less than 30 minutes;
S5. the obtained product of step S4 is filled into tablet press machine tabletted.
Beneficial effects of the present invention: radiation protection material of the present invention shield effectiveness in condition of equivalent thickness is obvious
Better than the non-lead protective materials being currently known, under same shield effectiveness, weight is lighter than other non-lead radiation protection materials, than current
Most light non-lead radiation protection material in the world using E.I.Du Pont Company's production is also light by 10% or more.Foreign study mechanism is ground at present
The properties of product of hair have certain limitation, undesirable in the high energy spectral coverage protection effect of ray, and heavier-weight, flexibility one
As, it is typically only capable to use at room temperature, price is high.And domestic existing radiation protection material be essentially all it is leaded, it is unleaded
Radiation protection material is very few, and the overwhelming majority leans on import, these unleaded radiation protection materials have certain protection effect to X-ray
Fruit cannot carry out shielding protection to gamma-rays.Radiation protection material of the present invention can be to X-ray, low-energyγ-ray all
Can shielding protection, Unit Weight, property at high and low temperature and in terms of have a clear superiority.
Specific embodiment
Technical solution of the present invention is clearly and completely described below in conjunction with specific embodiment, it is clear that described
Embodiment be only a part of the embodiment of the present invention, instead of all the embodiments.Based on the embodiments of the present invention, ability
Domain those of ordinary skill every other embodiment obtained, shall fall within the protection scope of the present invention.Involved in embodiment
Various mechanical, raw material can be obtained through commercial channels.
Embodiment one
Prepare raw material as following weight percent:
Tungsten: 35%;
Antimony: 10%;
Bismuth: 30%;
Tin: 5%;
Tantalum: 1%;
The organic silica gel that hardness is 60 degree: 19%;
S2. tungsten powder, antimony powder, bismuth meal are put into blender at normal temperature and are stirred evenly for use;
S3. tantalum powder and glass putty are added into macromolecule toughness substrate at normal temperature and are stirred evenly;
S4., mixed-powder obtained in step S2 is added into step S3 to the macromolecule toughness for being mixed with tantalum powder and glass putty
It is kneaded in matrix, mixing time is 40 minutes;
S5. the obtained product of step S4 is filled into tablet press machine tabletted.
Embodiment two
Prepare raw material as following weight percent:
Tungsten: 30%;
Antimony: 15%;
Bismuth: 35%;
Tin: 8%;
Tantalum: 1%;
The organic silica gel that hardness is 70 degree: 11%;
S2. tungsten powder, antimony powder, bismuth meal are put into blender at normal temperature and are stirred evenly for use;
S3. tantalum powder and glass putty are added into macromolecule toughness substrate at normal temperature and are stirred evenly;
S4., mixed-powder obtained in step S2 is added into step S3 to the macromolecule toughness for being mixed with tantalum powder and glass putty
It is kneaded in matrix, mixing time is 35 minutes;
S5. the obtained product of step S4 is filled into tablet press machine tabletted.
Embodiment three
Prepare raw material as following weight percent:
Tungsten: 40%;
Antimony: 5%;
Bismuth: 40%;
Tin: 2%;
Tantalum: 2%;
The organic silica gel that hardness is 70 degree: 11%;
S2. tungsten powder, antimony powder, bismuth meal are put into blender at normal temperature and are stirred evenly for use;
S3. gadolinium powder and glass putty are added into macromolecule toughness substrate at normal temperature and are stirred evenly;
S4., mixed-powder obtained in step S2 is added into step S3 to the macromolecule toughness for being mixed with tantalum powder and glass putty
It is kneaded in matrix, mixing time is 30 minutes;
S5. the obtained product of step S4 is filled into tablet press machine tabletted.
Example IV
Prepare raw material as following weight percent:
Tungsten: 15%;
Antimony: 20%;
Bismuth: 45%;
Tin: 5%;
Tantalum: 1%;
The organic silica gel that hardness is 60 degree: 14%;
S2. tungsten powder, antimony powder, bismuth meal are put into blender at normal temperature and are stirred evenly for use;
S3. gadolinium powder and glass putty are added into macromolecule toughness substrate at normal temperature and are stirred evenly;
S4., mixed-powder obtained in step S2 is added into step S3 to the macromolecule toughness for being mixed with tantalum powder and glass putty
It is kneaded in matrix, mixing time is 40 minutes;
S5. the obtained product of step S4 is filled into tablet press machine tabletted.
Difference of the finally obtained radiation protection material according to protective benefits, is suppressed with a thickness of 2-4mm.It is heretofore described
Macromolecule toughness substrate specifically can be rubber, resin, silica gel, the organic silica gel that preferred hardness is 60~70 degree.It is specific and
Speech, the radiation protection material that embodiment one to example IV obtains is with a thickness of 2mm.After measured, the radiation that above embodiments obtain
Protective materials X-ray, gamma ray shielding rate are as shown in table 1.
The radiation protection material shield effectiveness that 1. embodiment one to four of table obtains
The above measurement result shows that not only X-ray shield is had excellent performance radiation protection material of the present invention, also to γ
Ray has screening ability.
Radiation protection material use temperature range of the present invention can use outdoors between -40 DEG C~60 DEG C.
Under condition of equivalent thickness, the obtained radiation protection material weight of above-described embodiment using E.I.Du Pont Company than being produced most
Light non-lead radiation protection material is light by 10% or more.
In conclusion the present invention technically solves the shielding protection using non-lead radiation protection material to X-ray, again
There is shielding protection effect to gamma-rays.This novel non-lead radiation protection material is under the conditions of protection equivalent on an equal basis, than one
As material it is light by 10% or more, quality is flexible, and ageing-resistant, the service life is long, and use temperature range can be between -40 DEG C~60 DEG C, can
To use outdoors, it is easily processed into different protective equipments.Due to use China can mass production the elements such as rare earth, In
It is also lower than existing non-lead radiation protection material many on production cost.Compared with leaded or few lead radiation protection material, the material
The major ingredient auxiliary material of material is free of lead, asepsis environment-protecting, and no post-processing problem is conducive to environmental protection and user's health, belongs to new
Type green shielding protection material, is the choosing for preferably substituting leaded radiation protection material.
Claims (9)
1. a kind of radiation protection material, which is characterized in that count by weight percentage, composed of the following components: tungsten: 15% ~ 40%;
Antimony: 5% ~ 20%;Bismuth: 30% ~ 50%;Tin: 2% ~ 8%;Tantalum: 1% ~ 2%;Macromolecule toughness substrate: 8% ~ 20%.
2. a kind of radiation protection material according to claim 1, which is characterized in that the macromolecule toughness substrate is organic
Silica gel.
3. a kind of radiation protection material according to claim 2, which is characterized in that the organic silica gel hardness range is 60
~ 70 degree.
4. a kind of radiation protection material according to claim 1, which is characterized in that the purity of the tungsten is described greater than 98%
The purity of antimony is greater than 98%, and the purity of the bismuth is greater than 98%, and the purity of the tin is greater than 99%, and the purity of the tantalum is greater than 95%.
5. a kind of radiation protection material according to claim 1, which is characterized in that the weight percent of the tungsten is 35%;
The weight percent of the antimony is 10%;The weight percent of the bismuth is 30%;The weight percent of the tin is 5%;The tantalum
Weight percent be 1%;The weight percent of the macromolecule toughness substrate is 19%.
6. a kind of radiation protection material according to claim 1, which is characterized in that the weight percent of the tungsten is 30%;
The weight percent of the antimony is 15%;The weight percent of the bismuth is 35%;The weight percent of the tin is 8%;It is described
The weight percent of tantalum is 1%;The weight percent of the macromolecule toughness substrate is 11%.
7. a kind of radiation protection material according to claim 1, which is characterized in that the weight percent of the tungsten is 40%;
The weight percent of the antimony is 5%;The weight percent of the bismuth is 40%;The weight percent of the tin is 2%;The tantalum
Weight percent be 2%;The weight percent of the macromolecule toughness substrate is 11%.
8. a kind of radiation protection material according to claim 1, which is characterized in that the weight percent of the tungsten is 15%;
The weight percent of the antimony is 20%;The weight percent of the bismuth is 45%;The weight percent of the tin is 5%;The tantalum
Weight percent be 1%;The weight percent of the macromolecule toughness substrate is 14%.
9. a kind of manufacturing method of radiation protection material, which comprises the steps of:
S1. prepare raw material as following weight percent:
Tungsten: 15% ~ 40%;
Antimony: 5% ~ 20%;
Bismuth: 30% ~ 50%;
Tin: 2% ~ 8%;
Tantalum: 1% ~ 2%;
Macromolecule toughness substrate: 8% ~ 20%;
S2. tungsten powder, antimony powder, bismuth meal are put into blender at normal temperature and are stirred evenly for use;
S3. tantalum powder and glass putty are added into macromolecule toughness substrate at normal temperature and are stirred evenly;
S4., mixed-powder obtained in step S2 is added into step S3 to the macromolecule toughness substrate for being mixed with tantalum powder and glass putty
Middle mixing, mixing time are no less than 30 minutes;
S5. the obtained product of step S4 is filled into tablet press machine tabletted.
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CN110028794A (en) * | 2019-03-28 | 2019-07-19 | 中国辐射防护研究院 | A kind of tungsten lead doped silicon rubber-base flexible material having radiation shield function and preparation method |
CN113674887A (en) * | 2021-08-20 | 2021-11-19 | 山东双鹰医疗器械有限公司 | Lead-free X-ray and gamma-ray protection hard material and preparation method thereof |
CN115162016A (en) * | 2022-08-01 | 2022-10-11 | 英纳能(北京)特种材料科技有限公司 | Tin/antimony composite coating and preparation method thereof, and tin/antimony composite coating fabric and preparation method and application thereof |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
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WO2005017556A2 (en) * | 2003-07-18 | 2005-02-24 | Advanced Shielding Components, Llc | Lightweight rigid structural compositions with integral radiation shielding including lead-free structural compositions |
CN1748263A (en) * | 2002-12-17 | 2006-03-15 | 兰爱克谢斯德国有限责任公司 | Lead-free mixture used as an additive for shielding radiation |
CN101137285A (en) * | 2007-10-12 | 2008-03-05 | 魏宗源 | Composite shielding material for medical X-ray protection |
CN101479809A (en) * | 2006-06-23 | 2009-07-08 | 马威格股份有限公司 | Laminated lead-free X-ray protection material |
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US10026513B2 (en) * | 2014-06-02 | 2018-07-17 | Turner Innovations, Llc. | Radiation shielding and processes for producing and using the same |
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CN1748263A (en) * | 2002-12-17 | 2006-03-15 | 兰爱克谢斯德国有限责任公司 | Lead-free mixture used as an additive for shielding radiation |
WO2005017556A2 (en) * | 2003-07-18 | 2005-02-24 | Advanced Shielding Components, Llc | Lightweight rigid structural compositions with integral radiation shielding including lead-free structural compositions |
CN101479809A (en) * | 2006-06-23 | 2009-07-08 | 马威格股份有限公司 | Laminated lead-free X-ray protection material |
CN101137285A (en) * | 2007-10-12 | 2008-03-05 | 魏宗源 | Composite shielding material for medical X-ray protection |
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