KR20090010581A - Fabric from radioactive ray shield - Google Patents

Fabric from radioactive ray shield Download PDF

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KR20090010581A
KR20090010581A KR1020070073819A KR20070073819A KR20090010581A KR 20090010581 A KR20090010581 A KR 20090010581A KR 1020070073819 A KR1020070073819 A KR 1020070073819A KR 20070073819 A KR20070073819 A KR 20070073819A KR 20090010581 A KR20090010581 A KR 20090010581A
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radiation
shielding layer
neutron
weight
radiation shielding
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KR1020070073819A
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Korean (ko)
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지상협
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지상협
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    • AHUMAN NECESSITIES
    • A61MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61BDIAGNOSIS; SURGERY; IDENTIFICATION
    • A61B6/00Apparatus or devices for radiation diagnosis; Apparatus or devices for radiation diagnosis combined with radiation therapy equipment
    • A61B6/10Safety means specially adapted therefor
    • A61B6/107Protection against radiation, e.g. shielding
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F1/00Shielding characterised by the composition of the materials
    • G21F1/02Selection of uniform shielding materials
    • G21F1/10Organic substances; Dispersions in organic carriers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F1/00Shielding characterised by the composition of the materials
    • G21F1/12Laminated shielding materials
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F3/00Shielding characterised by its physical form, e.g. granules, or shape of the material
    • G21F3/02Clothing

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  • Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Medical Informatics (AREA)
  • Pathology (AREA)
  • Molecular Biology (AREA)
  • Optics & Photonics (AREA)
  • Biophysics (AREA)
  • Radiology & Medical Imaging (AREA)
  • Biomedical Technology (AREA)
  • Heart & Thoracic Surgery (AREA)
  • Nuclear Medicine, Radiotherapy & Molecular Imaging (AREA)
  • Surgery (AREA)
  • Animal Behavior & Ethology (AREA)
  • General Health & Medical Sciences (AREA)
  • Public Health (AREA)
  • Veterinary Medicine (AREA)
  • Chemical & Material Sciences (AREA)
  • Dispersion Chemistry (AREA)
  • Compositions Of Macromolecular Compounds (AREA)

Abstract

The present invention provides a shielding suit made of radiation shielding fibers infused with paraffin during maintenance work and operation of a radiation neutron generating zone in a nuclear power plant or nuclear power plant to prevent radiation and / or neutron exposure. The present invention is to solve the above problems, first to form a flexible neutron shielding layer by uniformly heat-mixing and extruding the molten paraffin / polyolefin resin and metal nanoparticles together, the radiation shielding layer on both sides of the flexible neutron shielding layer The radiation shielding layer is formed with a coating layer made of a polyurethane resin on the surface of the fabric, and the barium sulfate and the organic iodine-based radiocontrast compound are uniformly dispersed in powder form inside the coating layer.

Description

Radiation shielding fiber {Fabric from radioactive ray shield}

Places where there is a lot of radiation, or where there is a lot of radiation, for example, those working in the radiation zones of nuclear power plants or in industrial sites handling radiation transmission test equipment are always at risk of exposure to radiation.

It is well known that radiation, such as x-rays and gamma rays, causes many serious diseases and disorders, including carcinogenesis, genetic disorders, and cataracts. Accordingly, in 1934, the International Commission on Radiation Protection was launched to limit the use of radiation (0.2 R / day), and in 1977 the International Recommendation on Radiation Protection (ICRP-26) was adopted, followed by X-ray diagnosis, treatment and nuclear Guidelines for reducing the exposure of patients, workers and carers to medicine have been published, and countries have enacted laws on the use of radiation.

As such, exposure to radiation is very harmful to the human body, so it should be made as limited as possible. However, people who directly or indirectly deal with radiation, such as radiologists, doctors, and nuclear power personnel in hospitals, may be exposed to radiation continuously because of their work characteristics. Should be

Therefore, in order to protect the workforce when working in places with high radiation such as repair or inspection of nuclear power plants, radiation shielding suits are worn to protect from the danger of exposure.

The present invention relates to a shield member for the production of such radiation shielding clothing.

As a method for shielding the radiation exposure, it is common to wear a sheet-like gown formed by dispersing lead components in a rubber and then extruding them. However, gowns made in this way are effective for radiation shielding, but are very heavy, such as 5-10 kg, and have a poor fit.

At this time, the thickness of the lead plate should be thick enough to block the radiation, but if it is too thick, the shielding clothing is heavy, making it difficult to wear and making the operation very uncomfortable.

The working environment in which radiation is generated is not always constant. In other words, if you are working near a nuclear reactor or in a workshop that handles low-radiation wastes, wear lighter clothing that is lighter and less disruptive than working with thick lead shields. It is preferable.

However, until now, the only option was to use thick lead shields that block radiation, or to use protective clothing that protects against dust dust.

That is, there was no convenient shielding suit that shielded only a small degree of radiation in the working environment with low radiation generation and increased work activity.

As a lighter shielding suit, US Patent No. 3,194,239 discloses a method of manufacturing radiation absorbing fibers using an alloy wire for radiation absorption, but this has a problem of poor flexibility and radiation shielding properties.

It is an object of the present invention to provide a convenient shielding suit which can shield an appropriate amount of radiation without the use of lead that is harmful to the human body, and is easy to work.

The present invention is to solve the above problem, to effectively block the radiation by laminating a neutron shielding layer between the radiation shielding layers. The neutron shielding layer is formed by uniformly heat-mixing molten paraffin / polyolefin resin and metal nanoparticles together by extrusion / cooling. The neutron shielding layer is composed of polyolefin and solid paraffin in the pores so that the metal nanoparticles are evenly dispersed. The radiation shielding layer forms a coating layer on the surface of the fabric, and the coating layer uniformly disperses barium sulfate and an organic iodine-based radiocontrast compound in powder form. In the present invention, the radiation shielding member may increase the selection width by adjusting the thickness of the neutron shielding layer according to the radiation neutron energy intensity.

Specifically,

The present invention is a first radiation shielding layer (1); Neutron shielding layer 2; And a second radiation shielding layer 1,

The first and second radiation shielding layer is formed with a coating layer made of polyurethane resin on the surface of the fabric, the barium sulfate and the organic iodine-based radiographic compound is uniformly dispersed in powder form inside the coating layer,

The neutron shielding layer comprises at least one element of gadolinium, boron, lithium having 100 parts by weight of a resin mixture composed of 10 to 50% by weight of thermoplastic polyolefin and 50 to 90% by weight of molten paraffin and 1 to 10 parts by weight of nanoparticles. It is characterized in that the gel sheet having fine and uniform pores obtained by uniformly mixing at high temperature and extrusion / cooling.

In addition, in the neutron shielding layer of the present invention, the pore size occupied by paraffin is 0.1 to 1 μm, and the porosity is 30 to 90%.

Radiation exposure of equipment workers and maintenance workers by radiation workers during operation of nuclear power plants or nuclear facilities can be prevented in advance, and safety hazards can be secured for nuclear workers by reducing hazards to health risks.

Detailed embodiments of the invention are disclosed herein. It should be understood, however, that the disclosed embodiments may be practiced in various forms only as illustrations of the invention. Accordingly, the detailed description disclosed herein should not be construed as limiting, but merely as a basis for teaching those skilled in the art to the basis of the claims and how to make and / or use the invention.

In the radiation shielding layer 1 according to the present invention, a coating layer made of a polyurethane resin is formed on a fabric surface, and barium sulfate (BaSO 4) and an organic iodine-based radiocontrast compound are uniformly dispersed in a powder form inside the coating layer. .

Barium sulfate is a radiopharmaceutical that is safe for the human body used for taking pictures of the digestive organs, and has a relatively excellent axon shielding (absorption) effect. However, since barium sulfate has a very high density of 4.5 g / cm 3 and poor compatibility with polyurethane resins, barium sulfate powder is dispersed in polyurethane resin and treated on fabric surface as in the prior art. Poor acidity makes it difficult to form a radiation shielding layer in which barium sulfate is uniformly distributed. Therefore, in order to impart good radiation shielding effect to the fabric by using barium sulfate, more than necessary barium sulfate may be added, thereby placing a great burden on weight and wearability.

In order to overcome the above problems, in the radiation shielding layer 1 of the present invention, a coating layer made of a polyurethane resin is formed on the surface thereof, and an organic iodine-based radiation contrast compound is uniformly dispersed in a powder form inside the coating layer. .

The organic iodine-based radiocontrast compounds include imidotrizoic acid, iooxyglic acid, iophthalamic acid, iotrocitic acid, iotrolic acid, iopanoic acid, iomidol, iohexel, sodium iodate, iodineamide, The well-known organic iodine type compound used as a contrast absorbing agent, such as iodoxamic acid, can be used individually or in mixture of these.

These organic iodine-based radiocontrast compounds absorb radiation and significantly weaken their transmittance. Unlike barium sulfate, the organic iodine-based radiocontrast compounds do not have a large difference in density from polyurethane resins and form hydrogen bonds with polyurethane resins. Very good and safe even in contact with the human body. However, it is preferable to use the mixture with barium sulfate for cost reduction, but the mixing weight ratio (B / A) of barium sulfate (A) and the organic iodine-based radiocontrast compound (B) is 1/1000 to 1/2 It is preferable in view of economical efficiency and uniformity of radiation shielding efficacy.

In this way, when the barium sulfate and the organic iodine-based radiocontrast compound are dispersed in a polyurethane resin and applied to the fabric, a fabric that is harmless to the human body and has good radiation shielding property can be obtained. In addition, in order to further improve the radiation shielding performance of the present invention, alkaline earth metal compounds such as calcium hydroxide, calcium carbonate, magnesium hydroxide, magnesium oxide, magnesium carbonate, bismuth compounds such as bismuth oxycarbonate, or the like may be mixed alone or in combination when forming the coating layer. It may be further added, and an adhesive layer may first be formed on the fabric surface prior to forming the coating layer to form a solid radiation shielding coating layer.

In general, coating processing of fibers has a long history, and processing methods have been developed according to various products. In the present invention, the coating technology developed so far is used, and the target fabric of the coating is nylon, polyester, and the like, and acrylic, vinyl, cotton, rayon, or other blends with other fibers. The coating method and the machine are selected in consideration of the state of the metal, the characteristics of the coating agent, the coating amount, and the like.

The general coating method can be divided into a transfer coating method (Laminate) for attaching a film of resin to the fiber and a direct coating method to form a film by directing the resin on the fabric, the present invention uses a direct coating method, Floating knife method, by installing the knife on the roller to adjust the amount of coating by adjusting the distance between the roller and knife, knife on belt method, reversible roll coating method, etc. may be selectively used.

In the neutron shielding layer 2 of the present invention, the thermoplastic polyolefin is a crystalline homopolymer or copolymer obtained by polymerizing ethylene, propylene, 1-butene, 4-methylpentene, 1 hexene, and the like, and polyolefins such as copolymers thereof; Vinyl chloride resin, vinyl acetate resin, polystyrene, fluorine resin, polyamide resin, polyacetal resin, polycarbonate, thermoplastic polyimide, thermoplastic polyurethane, polyphenylene salpide, polyvinyl alcohol, and the like. Among these, polyolefins, such as polyethylene and a polypropylene, are preferable from a moldability and economical viewpoint.

Specifically, the neutron shielding layer 2 of the present invention can be prepared by heating and dissolving a polyolefin in a solvent, and any solvent can be used as long as it has a neutron shielding ability. Nonvolatile solvents such as are preferred.

In the neutron shielding layer, at least one or more elements of gadolinium, boron, and lithium having a particle size of 1 to 10 parts by weight relative to 100 parts by weight of the resin compound composed of thermoplastic polyolefin and molten paraffin are uniformly dispersed. The metal further increases the neutron shielding ability. When the metal is mixed to less than 1 part by weight, the increase in neutron shielding ability is insufficient, and when mixed to 10 parts by weight or more, it is difficult to obtain a uniform pore structure. The size of the metal particles should be less than the nano-size to be evenly dispersed in paraffin in the pores. Specific examples of the metal particles are described below.

Heating dissolution is performed while stirring at a temperature at which the polyolefin is completely dissolved in a solvent. The temperature varies depending on the polymer and the solvent used, but is, for example, in the range of 140 to 250 ° C in the case of polyethylene. The concentration of the polyolefin solution is 10 to 50% by weight, preferably 10 to 40% by weight. When shaping into a sheet shape at a concentration of less than 10% by weight, the swell and neck-in are large at the die exit, making the sheet difficult to form. On the other hand, when concentration exceeds 50 weight%, adjustment of a uniform solution becomes difficult.

Next, the solution of this polyolefin is extruded and cooled from die | dye, and a gel sheet is shape | molded. As the die, a sheet die having a rectangular clasp shape is usually used, but a hollow cylindrical die, an inflation die, or the like can also be used. The die cap in the case of using a sheet die is usually 0.1 to 5 mm, and is heated to 140 to 250 ° C at the time of extrusion molding. The extrusion speed at this time is usually 20 to 30 cm / min to 2 to 3 m / min.

In this way, the solution extruded from the die is formed into a gel sheet by cooling. Cooling is preferably performed at a rate of less than 50 ° C./minute up to at least the gelled temperature. The cooling rate is slowed down to increase the crystallinity, form dense bubble units, and solidify the molten paraffin. As the cooling method, cold air, cooling water, a method of directly contacting the cooling medium, a method of contacting a roll cooled with a refrigerant, and the like can be used.

The pore size of the gel sheet is preferably 0.001 to 1㎛ and porosity is 30 to 90%. If the porosity is less than 30%, the radiation shielding effect is inferior. If the porosity is 90% or more, the durability of the sheet is deteriorated.

The gel sheet can be adjusted in thickness by applying a tensile stress or a compressive stress and then a tensile stress, if necessary. Specifically, the film is drawn after stretching or stretching. Stretching is performed at a predetermined magnification by the usual tenter method, roll method, inflation method, rolling method, or a combination of these methods.

Hereinafter, the present invention will be described using specific examples.

<Example>

(1) radiation shielding layer

First, 100 parts by weight of the two-component polyurethane resin, 40 parts by weight of methyl ethyl ketone, 20 parts by weight of toluene, 5 parts by weight of the crosslinking agent and 5 parts by weight of the acrylic resin are uniformly mixed, and then the poly is removed using a floating knife (thickness 1.5 mm). The surface of the ester fabric was applied in an amount of 50 g / m 2 and dried at 130 ° C. for 60 seconds to form an adhesive layer. Subsequently, 100 parts by weight of the one-component polyurethane resin, 200 parts by weight of barium sulfate, 50 parts by weight of imidotrizoic acid, 40 parts by weight of methyl ethyl ketone, and 20 parts by weight of toluene were mixed uniformly, and then a floating knife (thickness) was formed on the formed adhesive layer. 2.0 mm) was applied in an amount of 30 g / ㎡ and dried for 60 seconds at 130 ℃ to prepare a fabric with a radiation shielding layer.

(2) neutron shielding layer

A weight average molecular weight (Mw) of 6.8 x 10 5 polyethylene (PE) 17 parts by weight of the raw material resin, 83 parts by weight of molten paraffin, and 5 parts by weight of nano-size lithium metal powder were uniformly mixed to prepare a mixed solution. Next, this liquid mixture was filled into the autoclave with a stirrer, and it stirred at 200 degreeC for 90 minutes, and obtained the uniform solution.

This solution was extruded from T-die at 200 degreeC with the 45-mm-diameter extruder, contacted with the 20 degreeC cooling roll, and the neutron shielding layer was shape | molded with the gel sheet of thickness 1.8mm-5mm.

The pore size of the neutron shielding layer was 0.2 µm and the porosity (measured by gravimetric method) was 83%.

A neutron shielding layer was laminated between the prepared radiation shielding layers to prepare a fiber for radiation shielding. The radiation shielding fiber of the present invention prepared as described above is formed to seal the neutron shielding layer to seal the neutron shielding layer in order to prevent leakage of oil and the like and to prevent the fiber from pulling out.

The prepared fiber was subjected to radiation shielding experiments in the laboratory. The fiber was cut into 50 × 50 cm, and then the radiation shielding rate was measured 10 times each time according to the source and the average energy shown in Table 1 below, and then the average value and the variation range are shown in Table 1.

% Change = Maximum radiation shielding rate measured-Minimum radiation shielding rate measured

TABLE 1

Radiation class sailor Average energy Shielding rate Change Alpha Line Po-210 5,300 keV 100% 0% beta rays Sr-90 69keV 99% One% Ti-204 72.4keV 100% 0% Gamma rays Am-241 60keV 98% 2% Co-57 122keV 94% 4% X-ray Braking radiation 40 kV 100% 0% 60 kV 100% 0% 80 kV 97% 3% 100 kV 95% 4% 120 kV 95% 5%

As another embodiment of the present invention by extruding the neutron shielding layer between the impermeable polyethylene resin to form a neutron shielding layer laminated in a sealed form up and down, and forming a radiation shielding layer above and below the radiation shielding fiber There is also this to get. In this case, the impervious polyethylene resin may be used in a thickness of 0.2 mm to 10 mm.

The impermeable resin may include at least one element of polyolefin resin or gadolinium, boron, lithium having an average particle size of less than 10㎛, in particular less than 5㎛. Substances containing the above elements include gadolinium oxide Gd 2 O 3 , gadolinium gallium and garnet Gd 3 Ga 5 O 12 , gadolinium ferrite GdFeO 3 , Gd 3 Fe 5 O 12 , gadolinium hydroxide Gd (OH) 3 , and cerium Activated gadolinium silicate Gd 2 SiO 5 : Ce, europium activated borate Gadolinium GdBO 3 : Eu, europium activated gadolinium oxide Gd 2 O 3 : Eu, europium activated gadolinium sulfate Gd 2 O 2 S : Eu, europium-activated gadolinium Gd 3 Al 5 O 12 : Eu, europium-activated gallium acid gadolinium Gd 3 Ga 5 O 12 : Eu, europium-activated vanadium acid gadolinium GdVO 4 : Eu And gallium gadolinium Gd 3 Ga 5 O 12 : Ce, Cr, terbium-activated gadolinium oxide Gd 2 O 3 : Tb, terbium-activated gadolinium sulfate Gd 2 O 2 S: Tb, Gadolinium Sulfate Gd 2 O 2 S Activated with Furaseom: Pr, terbium-activated gallium acid gadolinium Gd 3 Ga 5 O 12 : Tb, terbium-activated aluminate gadolinium Gd 3 Al 5 O 12 : Tb, boron carbide B 4 C, boron nitride BN, boron phosphide BP, sulfur yellow Boron B 2 S 3 , boron phosphate BPO 4 , boron oxide B 2 O 3 , lithium oxide Li 2 O, lithium peroxide Li 2 O 2 , lithium aluminate LiAlO 2 , lithium metaborate LiBO 2 , lithium tetraborate Li 2 B 4 O 7 , Lithium Germanic acid Li 2 GeO 3 , Lithium molybdate Li 2 MoO 4 , Lithium niobate LiNbO 3 , Lithium metasilicate Li 2 SiO 3 , Lithium titanate LiTaO 3 , Lithium titanate Li 2 TiO 3 , Lithium vanadate LiVO 3 , lithium tungstate LiWO 4 , lithium zirconate Li 2 ZrO 3 , lithium nitride Li 3 N, lithium hydroxide LiOH.H 2 O, methoxy lithium LiOCH 3 .

<Eutron Shielding Capability Evaluation>

Table 2 below shows the results of the shielding performance of the radiation shielding fibers prepared according to the present invention. A neutron beam outlet of a certain size was made, and a detector capable of measuring the intensity of the neutron was placed at a constant distance (5 cm) from the outlet, and the intensity of the neutron penetrating the fiber was measured. At this time, the thickness of the fiber was measured with a detector. The measured intensity was calculated as the neutron absorption cross-sectional area factor.

The method of calculating the neutron absorption cross section coefficient is as follows.

I / I 0 = L -μx or μ = [log (I 0 / I)] / x

(I 0 : incident beam, I: transmission beam, x: transmission thickness, μ: suction area coefficient)

Table 2: Test Results

Thickness (cm) count μ (cm -1 ) 0.3 27,149 7.823 0.4 13,347 7,692 0.5 8,533 7.217 0.7 2,956 7.186 0.9 1,291 7.071 1.5 525 6.888 2.0 411 5.339 2.5 340 4.732

As a result of the test, the present invention seems to increase the shielding effect by attenuating energy by scattering radiation in paraffin in the pores of the radiation shielding material having uniform pores in addition to the shielding effect by the metal powder in the resin. In addition, the shielding effect was further increased by the metal powder dispersed in paraffin in the voids.

1 is a cross-sectional view for explaining the structure of the radiation shielding material of the present invention.

Figure 2 is a cross-sectional view for explaining the pore structure of the radiation shielding material of the present invention.

* Explanation of reference marks *

A: pore B: polyolefin resin layer

Claims (2)

A first radiation shielding layer 1; Neutron shielding layer 2; And It consists of the 2nd radiation shielding layer 1, The first and second radiation shielding layer is formed with a coating layer made of a polyurethane resin on the surface of the fabric, the barium sulfate and organic iodine-based radiocontrast compound is uniformly dispersed in powder form inside the coating layer, The neutron shielding layer comprises at least one element of gadolinium, boron, lithium having 100 parts by weight of a resin blend consisting of 10 to 50% by weight of thermoplastic polyolefin and 50 to 90% by weight of molten paraffin and 1 to 10 parts by weight of nanoparticles. And a gel-like sheet having fine and uniform pores obtained by uniformly mixing at high temperature and extruding / cooling. The radiation shielding material of claim 1, wherein the neutron shielding layer has a pore size of 0.1 to 1 µm and a porosity of 30 to 90%.
KR1020070073819A 2007-07-24 2007-07-24 Fabric from radioactive ray shield KR20090010581A (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102157214A (en) * 2010-12-02 2011-08-17 卜庆革 Silver-plated cloth with rare earth-shielding composite layer, preparation method thereof and clothes made of same

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102157214A (en) * 2010-12-02 2011-08-17 卜庆革 Silver-plated cloth with rare earth-shielding composite layer, preparation method thereof and clothes made of same

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