WO2015199276A1 - 방사선 차폐용 조성물 및 그의 제조방법 - Google Patents
방사선 차폐용 조성물 및 그의 제조방법 Download PDFInfo
- Publication number
- WO2015199276A1 WO2015199276A1 PCT/KR2014/006526 KR2014006526W WO2015199276A1 WO 2015199276 A1 WO2015199276 A1 WO 2015199276A1 KR 2014006526 W KR2014006526 W KR 2014006526W WO 2015199276 A1 WO2015199276 A1 WO 2015199276A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- radiation shielding
- weight
- parts
- resin
- oxide
- Prior art date
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Images
Classifications
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- G21F1/00—Shielding characterised by the composition of the materials
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- G21F1/125—Laminated shielding materials comprising metals
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- C08L2205/035—Polymer mixtures characterised by other features containing three or more polymers in a blend containing four or more polymers in a blend
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Definitions
- the present invention relates to a radiation shielding composition and a method for manufacturing the same, and more particularly, for shielding radiation that can shield not only radiation, such as alpha, beta, protons, gamma rays, X-rays, but also neutrons without using lead.
- Radioactive materials exist in nature, and are made artificially for industrial and medical purposes, and there are various kinds.
- Ionizing radiation refers to radiation such as alpha, beta, protons, neutrons, gamma rays, and X-rays, which cause ionization as it passes through the material.
- Alpha rays are absorbed and blocked by a material with a paper thickness.
- the beta rays are known to be larger than the alpha rays, but can generally be blocked by thin aluminum foil or plastic plates.
- Gamma rays are electromagnetic waves with higher energy than X-rays resulting from the collapse or transformation of the nucleus, and have a very strong penetrating power. Such gamma rays may be blocked through concrete or high density metal materials such as iron and lead, but when metal materials are used, the weight of the shielding material is increased due to their high density.
- Neutrons occur when a nucleus collapses or divides, and they do not charge, but fast neutrons have a large energy of 1 MeV or more.
- a shielding material in which a neutron absorbing material is mixed for absorbing thermal neutrons having a reduced energy such as a high speed neutron is required.
- gamma rays or neutrons can act directly on atoms or molecules, altering the major structure of DNA or proteins, and when acting on the germ cells of an organism, they can induce mutations and increase the probability of causing malformations. If you do it can cause diseases such as cancer and moreover, the thermal neutron has a problem of radioactively polluting the surrounding environment by radiation of the surrounding material. Therefore, in the field where radiation is applied, a radiation shielding material capable of shielding gamma rays or neutrons harmful to humans and the environment is indispensable. It is known that a conventional gamma ray shielding material can obtain a gamma ray shielding effect using a material including iron, lead, cement, and the like.
- neutron microabsorption such as paraffin, carbon, boron, boron, lithium, and gadolinium, which has a high content of light atomic numbers such as hydrogen (H), oxygen (O), and carbon (C), which have similar masses, and is excellent in absorbing neutrons
- H hydrogen
- O oxygen
- C carbon
- X-rays discovered by Roentgen are currently used in a wide range of industries and medically.However, when these radiations are exposed to humans, radiographers, schools, research institutes, and nuclear power plant operators who operate medical doctors and X-ray inspection equipment, Due to the nature of work, radiation can be continuously exposed.
- the lead gown which is worn as a protective garment for the conventional radiation shielding, is used by dispersing lead in vinyl chloride resin (PVC) and rubber (RUBBER) and then bonding it onto a sheet through an extrusion method. It is heavy, about 10kg, poor fit, poor activity and almost no wearing.
- Korean Patent Publication No. 10-2004-0093878 introduces a radiation shielding fiber manufacturing technology using organic iodine-based materials such as barium sulfate, which is free from harm to humans by lead and achieves light weight, but has an effect on neutron shielding. Barium sulfate itself does not have excellent shielding effect against gamma rays or X-rays, and Patent Publication No. 10-2010-0047510 discloses a technique for mixing nanoparticle-sized radiation shielding materials with a polymer.
- the technology to increase the probability of collision with radiation has been introduced, but it is advantageous to light weight, but some lead components are applied, which is harmful to human body.
- the metal nanoparticles are used in the ratio of up to 20%, the ratio of polymer is excellent even though the dispersing effect is excellent.
- This high air gap is large, considering the high penetration of radiation Part of the surface shielding effect and insufficient, it is oxidized boron neutron shielding (B 2 O 3) a neutron shield having a broad energy distribution by using a single material has a limit economical as high is to apply to the fiber the nano metal particles There is a disadvantage that does not correspond to.
- Korean patent yarn 1988-0012950 there is a problem in weight or human hazard in the method of manufacturing radiation shielding fiber, and in application number 10-2006-0070088, the shielding fiber is introduced by wet spinning using barium sulfate (BaSO 4 ).
- barium sulfate BaSO 4
- the high density of hydrogen atoms and the use of paraffins have advantages in shielding neutrons, but they are disadvantageous in their ability to bond with fibers, making them unsuitable for use as protective garments or fibers, making them unsuitable for use and applying organic iodine-based materials to gamma rays or X-rays.
- 20-1999-0023705 Introduction technology is a method of particle radiation through the use of porous absorbers. About dashed lacking for effective and other radiation.
- a lead-free radiation shielding material is introduced, but antimony trioxide (Sb 2 O 3 ) and tin (Sn) powder are used. There is this.
- An object of the present invention is to solve the above problems, including a polyether ether ketone (PEEK) resin without the use of lead, radiation that can be shielded to neutrons as well as radiation such as alpha, beta, protons, gamma rays, X-rays It is to provide a composition for shielding and a method of manufacturing the same.
- PEEK polyether ether ketone
- 100 parts by weight of the first resin including at least one selected from the group consisting of polyurethane resin, polysiloxane resin, silicone resin, fluorine resin, acrylic resin, and alkyd resin; 5 to 30 parts by weight of a second resin including at least one selected from the group consisting of polyvinyl alcohol (PVA), medium density polyethylene (MDPE), high density polyethylene (HDPE), and low density polyethylene (LDPE); 5 to 30 parts by weight of a polyether ether ketone (PEEK) resin powder; 5 to 80 parts by weight of the metal powder; 1 to 70 parts by weight of the metal oxide powder; Paraffin 1 to 50 parts by weight; 5 to 15 parts by weight of a boron compound; And 10 to 50 parts by weight of carbon powder; there is provided a radiation shielding composition comprising a.
- PVA polyvinyl alcohol
- MDPE medium density polyethylene
- HDPE high density polyethylene
- LDPE low density polyethylene
- PEEK polyether ether ketone
- the radiation shielding composition may further include 1 to 80 parts by weight of an inorganic additive based on 100 parts by weight of the first resin.
- the first resin may be a polyurethane resin.
- the metal powder may include at least one selected from the group consisting of aluminum, titanium, zirconium, scandium, yttrium, cobalt, tantalum, molybdenum, and tungsten.
- the metal oxide powder is composed of palladium oxide, iridium oxide, ruthenium oxide, osmium oxide, rhodium oxide, platinum oxide, iron oxide, nickel oxide, cobalt oxide, indium oxide, aluminum oxide, potassium oxide, titanium oxide, tungsten oxide, and magnesium oxide It may include one or more selected from the group.
- the inorganic additive may include one or more selected from the group consisting of calcium hydroxide, calcium carbonate, magnesium hydroxide, magnesium carbonate, barium chloride, and barium sulfate.
- the boron compound may include one or more selected from the group consisting of boric acid, cholemanite, zinc borate, boron carbide, boron nitride and boron oxide.
- the carbon powder may include at least one selected from the group consisting of fullerenes, carbon nanofibers, and carbon nanotubes.
- the radiation shielding composition may further include 10 to 100 parts by weight of a curing agent based on 100 parts by weight of the first resin.
- a radiation shielding sheet including the radiation shielding composition may be provided.
- the textile textile
- the radiation shielding sheet formed on the textile.
- the textile may be any one of woven, knitted and nonwoven fabrics.
- the textile may be one containing at least one selected from polyester fibers, nylon fibers, and aramid fibers.
- the radiation shielding textile composite may further include an adhesive layer between the textile and the radiation shielding sheet.
- the radiation shielding textile composite may be used in one or more of a radiation shielding bag, protective equipment and protective clothing.
- the first textile A first adhesive layer disposed on the first textile; A radiation shielding sheet disposed on the first adhesive layer;
- a second adhesive layer disposed on the radiation shielding sheet; And a second textile disposed on the second adhesive layer; a radiation shielding textile composite may include a laminate stacked sequentially.
- the step of coating a shielding composition prepared according to the above-described method in the side dam (side dam) including a release paper on the bottom surface step 1; Drying the coated composition of step 1 to prepare a sheet for radiation shielding (step 2); And bonding a textile to the radiation shielding sheet to produce a radiation shielding textile composite (step 3).
- a method for producing a radiation shielding textile composite comprising a.
- Radiation shielding sheet comprising a radiation shielding composition of the present invention, radiation shielding textile composites, protective clothing comprising the same, including a polyether ether ketone (PEEK) resin without the use of alpha, beta, protons
- PEEK polyether ether ketone
- FIG. 1 is a cross-sectional view of the radiation shielding textile composite of the present invention.
- FIG. 2 is a cross-sectional view of another radiation shielding textile composite of the present invention.
- Figure 3 schematically shows a side dam coating system used in the manufacture of the radiation shielding sheet of the present invention.
- Figure 4 is a side view schematically showing a radiation shielding sheet and a side dam manufactured using a coating system of the side dam method, 10 is the side dam, 20 is the first release film, 30 is the radiation shielding sheet, 40 is the second It is a release film.
- 5 is a view schematically showing a structure of a side dam, 10 is a side dam, and 20 is a first release film.
- the radiation shielding composition of the present invention comprises: 100 parts by weight of at least one first resin selected from the group consisting of polyurethane resins, polysiloxane resins, silicone resins, fluorine resins, acrylic resins, and alkyd resins; 5 to 30 parts by weight of at least one second resin selected from the group consisting of polyvinyl alcohol (PVA), medium density polyethylene (MDPE), high density polyethylene (HDPE), and low density polyethylene (LDPE); 5 to 30 parts by weight of a polyether ether ketone (PEEK) resin powder; 5 to 80 parts by weight of the metal powder; 1 to 70 parts by weight of the metal oxide powder; Paraffin 1 to 50 parts by weight; 5 to 15 parts by weight of a boron compound; And 10 to 50 parts by weight of carbon powder.
- PVA polyvinyl alcohol
- MDPE medium density polyethylene
- HDPE high density polyethylene
- LDPE low density polyethylene
- PEEK polyether ether ketone
- the specific gravity of the medium density polyethylene is 0.926 to 0.940
- the specific gravity of the high density polyethylene is 0.941 or more
- the specific gravity of the low density polyethylene may be 0.925 or less.
- the radiation shielding composition may further include 1 to 80 parts by weight of an inorganic additive based on 100 parts by weight of the first resin.
- a said 1st resin is a polyurethane resin.
- Polyurethane resin is suitable as a shielding material because it has excellent bonding strength with fiber material and has high durability and excellent flexibility.
- the high hydrogen density is effective in decelerating high-speed neutrons.
- polyurethane has the advantage of excellent bonding force with the fiber material, high durability, excellent flexibility.
- the second resin is a component that can enhance the neutron shielding effect.
- the neutron shielding effect may be inferior, and when more than 30 parts by weight, the bond strength with the fiber or when the sheet is made of strength It may be difficult to apply the shielding material is lowered.
- the metal powder may be aluminum, titanium, zirconium, scandium, yttrium, cobalt, tantalum, molybdenum, tungsten, or the like.
- the scope of the present invention is not limited thereto, and a metal having a relatively high electron density may be used.
- the metal oxide powder includes palladium oxide, iridium oxide, ruthenium oxide, osmium oxide, rhodium oxide, platinum oxide, iron oxide, nickel oxide, cobalt oxide, indium oxide, aluminum oxide, potassium oxide, titanium oxide, tungsten oxide, magnesium oxide, and the like. Can be used.
- the metal powder and the metal oxide powder may be used in the form of a composite, but the scope of the present invention is not limited thereto.
- the said metal powder and metal oxide powder whose particle diameter is 0.01-100 micrometers.
- the inorganic additive may be calcium hydroxide, calcium carbonate, magnesium hydroxide, magnesium carbonate, barium chloride, barium sulfate and the like. Inorganic additives such as these are safe for the human body, have a good radiation shielding effect, and preferably have a high density.
- the said inorganic additive whose particle diameter is 0.01-100 micrometers.
- the main component of the paraffin is a straight chain paraffinic hydrocarbon (CH 3 (CH 2 ) n CH 3 ), which is rich in carbon atoms, and the boron compound has a large and wide energy distribution with a fine absorption cross section, which is suitable for shielding neutrons.
- content of light atoms such as hydrogen, oxygen, and carbon similar in mass to a neutron, is high.
- the boron compound is boric acid (H 3 BO 3 ), colemanite (colemanite, Ca 2 O 14 B 6 H 10 ), zinc borate (Zn 2 O 14 , 5H 7 B 6 , Zn 4 O 8 B 2 H 2 And Zn 2 O 11 B 6 ), boron carbide (B 4 C), boron nitride (BN), boron oxide (B 2 O 3 ), and the like. More preferably, it can be used as a composite material of zinc borate and boron carbide.
- the carbon powder may be fullerene, carbon nanofibers, carbon nanotubes, or the like.
- the particle diameter is 5 to 200 nm.
- the radiation shielding composition may further include 10 to 100 parts by weight of a curing agent based on 100 parts by weight of the first resin.
- the said radiation shielding composition is a two-component composition, and when the said 1st resin contains 1 or more types of polyurethane resin, polysiloxane, fluorine resin, and alkyd resin which are thermosetting resins, it contains the said hardening
- a catalyst for promoting curing of the radiation shielding composition may be further included.
- the radiation shielding sheet of this invention contains the above-mentioned composition for radiation shielding.
- FIGS. 1 and 2 are schematic cross-sectional views of the radiation shielding textile composite of the present invention.
- the radiation shielding textile composite of the present invention will be described with reference to FIGS. 1 and 2.
- the radiation shielding textile composite of the present invention may comprise a textile and the radiation shielding sheet formed on the textile.
- the textiles may include wovens, knits, nonwovens, and the like.
- an adhesive layer may be further included between the textile and the radiation shielding sheet.
- the radiation shielding textile composite is a textile; An adhesive layer disposed on the textile; And a radiation shielding sheet disposed on the adhesive layer; may be a laminate laminated sequentially.
- the radiation shielding textile composite may include a first textile; A first adhesive layer disposed on the first textile; A radiation shielding sheet disposed on the first adhesive layer; A second adhesive layer disposed on the radiation shielding sheet; And a laminate in which second textiles disposed on the second adhesive layer are sequentially stacked.
- the textile may include polyester fibers, nylon fibers, aramid fibers and the like, but the scope of the present invention is not limited thereto.
- a separate adhesive layer for adhesion between the textile and the radiation shielding sheet may be omitted.
- the state where the radiation shielding sheet is semi-dried can be bonded by bonding the textile and completely dry and bonded by applying heat.
- the radiation shielding textile composite may be applied to any textile that requires radiation shielding, such as a radiation shielding bag, protective equipment, protective clothing, and the like.
- first resin selected from the group consisting of a polyurethane resin, a polysiloxane resin, a silicone resin, a fluorine resin, an acrylic resin, and an alkyd resin
- second resin selected from the group consisting of polyvinyl alcohol (PVA), medium density polyethylene (MDPE), high density polyethylene (HDPE), and low density polyethylene (LDPE)
- PEEK polyether ether ketone
- IPA isopropyl alcohol
- MEK methyl ethyl ketone
- TOLUENE toluene
- DMF dimethylformamide
- XYLENE xylene
- step b 5 to 80 parts by weight of the metal powder in the first preliminary composition; 1 to 70 parts by weight of the metal oxide powder; Paraffin 1 to 50 parts by weight; 5 to 15 parts by weight of a boron compound; And 10 to 50 parts by weight of carbon powder; to prepare a radiation shielding composition (step b).
- step b 1 to 80 parts by weight of the inorganic additive may be further included with respect to 100 parts by weight of the first resin.
- the paraffin, boron compound and carbon powder it is preferable to put the paraffin, boron compound and carbon powder to mix.
- the reason for performing the pre-mixing as described above is to improve the radiation shielding effect of the coating layer made of the radiation shielding composition of the present invention to achieve a uniform dispersion.
- Figure 3 schematically shows a side dam coating system used in the manufacture of the radiation shielding sheet of the present invention
- Figure 4 is a radiation shielding sheet manufactured using the side dam coating system
- Side view schematically showing the and side dams
- 5 is a sectional view schematically showing the structure of the side dam.
- a radiation shielding sheet will be described with reference to FIGS. 3 to 5.
- the radiation shielding composition 30 prepared according to the above method is coated in a predetermined thickness inside the side dam 10 including the first release film 20 on the bottom surface (Step 1). ).
- the coating of the radiation shielding composition 30 forms a coating layer with a predetermined thickness using a cylinder coater, and the thickness thereof is preferably 20 ⁇ m to 4000 ⁇ m, but may be adjusted to an appropriate thickness as necessary.
- the thickness of the composition coating layer formed according to the height (H) of the side dam 10 can be adjusted, and the first release film 20 is wound around the bottom surface of the side dam 10 to adjust the height of the bottom dam.
- the height H of 10 can be adjusted. In other words, when the height of the bottom surface is increased by winding the first release film 20 several times, the height H of the side dam 10 may be relatively low, thereby manufacturing a thin radiation shielding sheet. On the other hand, if the number of windings of the first release film 20 is small or if only the bottom surface is formed without sensing, the bottom surface is lowered, and the height H of the side dam 10 is increased, so that the relatively thick radiation shielding sheet Can be prepared.
- step 2 the coated composition 30 of step 1 is dried to prepare a radiation shielding sheet 30 (step 2).
- the drying is preferably performed at a temperature of 110 to 140 ° C. for 30 to 60 seconds, but the scope of the present invention is not limited thereto, and the drying temperature and time may be appropriately adjusted according to the thickness or component content of the composition.
- the second release film 40 may be attached and protected on the radiation shielding sheet 30.
- a radiation shielding sheet is manufactured in the same manner as described above (steps 1 and 2).
- the textile is bonded to the radiation shielding sheet to prepare a radiation shielding textile composite (step 3).
- the method may further include forming an adhesive layer on one surface of the radiation shielding sheet or textile.
- the method may further include drying and curing the adhesive layer.
- the adhesive layer may be formed to a uniform thickness using a comma knife, but the method of forming a uniform thickness is not limited thereto.
- the radiation shielding textile composite manufactured by the above method When used in the manufacture of protective equipment, bags, etc. for radiation shielding, the radiation shielding textile composites may be prepared in order to increase the shielding effect according to the radiation intensity. Overlapping may be used and, in some cases, may further comprise an endothelial textile on the side where the radiation-emitting contents contact.
- MDPE medium-density polyethylene
- HDPE high-density polyethylene
- LDPE low-density polyethylene
- PEEK polyether ether ketone
- MEK methyl ethyl ketone
- DMF dimethylformamide
- the solution containing the radiation shielding composition was coated to a thickness of 150 ⁇ m with a dam coater on a release film to prepare a radiation shielding film, and then dried and cured at 130 ° C. for 50 seconds. Subsequently, 100 parts by weight of a polyurethane adhesive resin (Double Chemical D-ACE 5038B product 2-component) on the surface layer of the radiation shielding film, and 10 parts by weight of a curing agent (Dongace Chemical D-ACE575), 20 parts by weight of DMF, 20 parts by weight of MEK.
- the adhesive was prepared by submixing, and the adhesive was applied to a thickness of 50 ⁇ m using a comma knife.
- a fabric comprising polyester fibers was laminated on the adhesive, dried and cured at 130 ° C. for 50 seconds to prepare a radiation shielding textile composite.
- the polyether ether ketone resin was mixed by 30 parts by weight based on 100 parts by weight of the polyurethane resin with the same product as in Example 1, and 20 parts by weight of methyl ethyl ketone (MEK) and toluene based on 100 parts by weight of polyurethane resin. 10 parts by weight and 20 parts by weight of dimethylformamide (DMF) were further added to prepare a primary preliminary composition.
- MEK methyl ethyl ketone
- DMF dimethylformamide
- the radiation shielding solution was prepared in the same manner as in Example 1, except that the solution containing the composition for radiation shielding was 350 ⁇ m instead of 150 ⁇ m in dam coater thickness, and the adhesive was 20 ⁇ m instead of 50 ⁇ m in thickness. Textile composites were prepared.
- Example 1 5 parts by weight of the polyether ether ketone Example 1 was mixed with respect to 100 parts by weight of the silicone resin, and 20 parts by weight of methyl ethyl ketone (MEK) and 30 parts by weight of toluene were added to 100 parts by weight of the silicone resin.
- MEK methyl ethyl ketone
- the primary preparative composition was prepared.
- molybdenum powder as a metal powder
- 10 parts by weight of tantalum powder 60 parts by weight of tungsten oxide (WO 3 ) powder as a metal oxide powder
- 10 parts by weight of barium sulfate (BaSO 4 ) as an inorganic additive were added to the first preliminary composition. Premixed.
- Example 2 Thereafter, 15 parts by weight of paraffin, 12 parts by weight of boron carbide (B 4 C), and 7 parts by weight of the same nano carbon fiber as in Example 1 were mixed with 100 parts by weight of acrylic resin to prepare a solution including a composition for radiation shielding. It was.
- a radiation shielding textile composite was prepared in the same manner and in the same manner as in Example 1, except that the polyurethane resin was used alone instead of the primary preliminary resin composition.
- a radiation shielding textile composite was prepared in the same manner and in the same manner as in Example 1, except that paraffin and nano carbon powder were not used.
- a radiation shielding textile composite was prepared in the same manner and in the same manner as in Example 1 except that only 35 parts by weight of tungsten was used alone.
- the radiation shielding textile composites prepared according to Examples 1 to 4 and Comparative Examples 1 to 3 were cut to 50 ⁇ 50 cm, and then the radiation shielding rate was determined according to the sources and average energy shown in Tables 1 and 2 below. After measuring 10 times each time by changing its position, the average value and the rate of change were measured and shown in Table 1 and Table 2 below.
- Equation 1 The meaning of the rate of change is shown in Equation 1 shown below.
- the radiation shielding fibers according to Comparative Examples 1 to 3 had a low shielding rate for radiation excluding alpha rays, and a high variation rate. Appeared.
- the radiation shielding textile composites according to Examples 1 to 4 of the present invention have excellent shielding effects in radiation of beta rays, gamma rays, and X-rays.
- the neutron shielding performance evaluation was performed on the radiation shielding textile composites prepared according to Examples 1 to 4 and Comparative Examples 1 to 3, and is shown in Table 3 below.
- Equation 2 The calculation method of the neutron absorption cross section coefficient is shown in Equation 2 below.
- Radiation shielding sheet comprising a radiation shielding composition of the present invention, radiation shielding textile composites, protective clothing comprising the same, including a polyether ether ketone (PEEK) resin without the use of alpha, beta, protons
- PEEK polyether ether ketone
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Abstract
Description
방사선 종류 | 선원 | 평균에너지 | 차 폐 율(%) | ||||||
실시예1 | 실시예 2 | 실시예 3 | 실시예 4 | 비교예1 | 비교예2 | 비교예3 | |||
알파선 | Po-210 | 5,300KeV | 100 | 100 | 100 | 100 | 100 | 100 | 100 |
베타선 | Sr-90 | 69KeV | 92 | 98 | 92 | 95 | 75 | 71 | 74 |
Ti-204 | 72.4KeV | 98 | 95 | 90 | 92 | 88 | 74 | 77 | |
감마선 | Am-241 | 60KeV | 94 | 98 | 92 | 90 | 82 | 78 | 75 |
Co-57 | 122KeV | 88 | 92 | 88 | 85 | 76 | 72 | 66 | |
Cs-137 | 661.7KeV | 78 | 83 | 85 | 81 | 64 | 67 | 48 | |
엑스선 | 제동 방사선 | 40kV | 100 | 100 | 100 | 100 | 96 | 95 | 86 |
60kV | 98 | 98 | 96 | 95 | 93 | 90 | 80 | ||
80kV | 98 | 96 | 92 | 93 | 90 | 84 | 76 | ||
100kV | 96 | 93 | 91 | 92 | 87 | 77 | 73 | ||
120kV | 92 | 92 | 90 | 90 | 78 | 65 | 63 |
방사선 종류 | 선원 | 평균에너지 | 변 동 률(%) | ||||||
실시예1 | 실시예 2 | 실시예 3 | 실시예 4 | 비교예1 | 비교예2 | 비교예3 | |||
알파선 | Po-210 | 5,300KeV | 0 | 0 | 0 | 0 | 0 | 0 | 0 |
베타선 | Sr-90 | 69KeV | 2 | 2 | 3 | 3 | 25 | 27 | 23 |
Ti-204 | 72.4KeV | 4 | 4 | 6 | 5 | 19 | 20 | 22 | |
감마선 | Am-241 | 60KeV | 3 | 2 | 3 | 4 | 17 | 21 | 24 |
Co-57 | 122KeV | 5 | 4 | 6 | 7 | 23 | 24 | 26 | |
Cs-137 | 661.7KeV | 7 | 6 | 8 | 10 | 28 | 28 | 31 | |
엑스선 | 제동 방사선 | 40kV | 0 | 0 | 0 | 0 | 20 | 19 | 22 |
60kV | 2 | 2 | 3 | 5 | 22 | 22 | 24 | ||
80kV | 4 | 2 | 5 | 3 | 23 | 25 | 28 | ||
100kV | 7 | 6 | 9 | 8 | 26 | 29 | 31 | ||
120kV | 7 | 8 | 9 | 10 | 30 | 32 | 34 |
열 중성자 흡수단면적계수μ(cm-1) | 실시예 1 | 실시예 2 | 실시예 3 | 실시예 4 | 비교예1 | 비교예2 | 비교예3 |
4.545 | 4.402 | 4.505 | 4.565 | 5.454 | 5.090 | 4.773 |
Claims (17)
- 폴리우레탄 수지, 폴리실록산 수지, 실리콘 수지, 불소 수지, 아크릴 수지, 및 알키드 수지로 이루어진 군에서 선택된 1종 이상을 포함하는 제1 수지 100중량부;폴리 비닐알콜(PVA), 중밀도 폴리에틸렌(MDPE), 고밀도 폴리에틸렌(HDPE), 및 저밀도 폴리 에틸렌(LDPE)로 이루어진 군에서 선택된 1종 이상을 포함하는 제2 수지 5 내지 30중량부;폴리에테르 에테르 케톤(PEEK) 수지 분말 5 내지 30중량부;금속 분말 5 내지 80중량부;금속 산화물 분말 1 내지 70중량부;파라핀 1 내지 50중량부;붕소 화합물 5 내지 15중량부; 및탄소 분말 10 내지 50중량부;를포함하는 방사선 차폐용 조성물.
- 제1항에 있어서,상기 방사선 차폐용 조성물이 상기 제1 수지 100중량부에 대하여 무기 첨가제 1 내지 80중량부를 추가로 포함하는 것을 특징으로 하는 방사선 차폐용 조성물.
- 제1항에 있어서,상기 제1 수지가 폴리우레탄 수지인 것을 특징으로 하는 방사선 차폐용 조성물.
- 제1항에 있어서,상기 금속 분말이 알루미늄, 티타늄, 지르코늄, 스칸듐, 이트륨, 코발트, 탄탈륨, 몰리브덴, 및 텅스텐으로 이루어진 군에서 선택된 1종 이상을 포함하는 것을 특징으로 하는 방사선 차폐용 조성물.
- 제1항에 있어서,상기 금속 산화물 분말이 산화 팔라듐, 산화이리듐, 산화루테늄, 산화오스뮴, 산화로듐, 산화백금, 산화철, 산화니켈, 산화코발트, 산화인듐, 산화알루미늄, 산화칼륨, 산화티타늄, 산화텅스텐 및 산화마그네슘로 이루어진 군에서 선택된 1종 이상을 포함하는 것을 특징으로 하는 방사선 차폐용 조성물.
- 제2항에 있어서,상기 무기 첨가제가 수산화칼슘, 탄산칼슘, 수산화마그네슘, 탄산마그네슘, 염화바륨, 및 황산바륨으로 이루어진 군에서 선택된 1종 이상을 포함하는 것을 특징으로 하는 방사선 차폐용 조성물.
- 제1항에 있어서,상기 붕소 화합물이 붕소산, 콜레마나이트, 붕산아연, 탄화붕소, 질화붕소 및 산화붕소로 이루어진 군에서 선택된 1종 이상을 포함하는 것을 특징으로 하는 방사선 차폐용 조성물.
- 제1항에 있어서,상기 탄소 분말이 풀러렌, 탄소나노섬유, 및 탄소나노튜브로 이루어진 군에서 선택된 1종 이상을 포함하는 것을 특징으로 하는 방사선 차폐용 조성물.
- 제1항에 있어서,상기 방사선 차폐용 조성물이 제1 수지 100중량부에 대해 경화제 10 내지 100중량부를 추가로 포함하는 것을 특징으로 하는 방사선 차폐용 조성물.
- 제1항에 따른 방사선 차폐용 조성물을 포함하는 방사선 차폐용 시트.
- 텍스타일(textile); 및상기 텍스타일상에 형성된 제9항에 따른 방사선 차폐용 시트;를 포함하는 방사선 차폐용 텍스타일 복합체.
- 제11항에 있어서,상기 텍스타일이 직물, 편물 및 부직포 중 어느 하나를 포함하는 것을 특징으로 하는 방사선 차폐용 텍스타일 복합체.
- 제11항에 있어서,상기 텍스타일이 폴리에스터 섬유, 나일론 섬유, 및 아라미드 섬유 중에서 선택된 1종 이상을 포함하는 것을 특징으로 하는 방사선 차폐용 텍스타일 복합체.
- 제11항에 있어서,상기 방사선 차폐용 텍스타일 복합체는 상기 텍스타일과 상기 방사선 차폐용 시트 사이에 접착층을 더 포함하는 것을 특징으로 하는 방사선 차폐용 텍스타일 복합체.
- 제11항에 있어서,상기 방사선 차폐용 텍스타일 복합체가 방사선 차폐용 백(bag), 보호장구 및 보호의류 중 1종 이상에 사용되는 것을 특징으로 하는 방사선 차폐용 텍스타일 복합체.
- 제1 텍스타일;상기 제1 텍스타일상에 배치된 제1 접착층;상기 제1 접착층 상에 배치된 방사선 차폐용 시트;상기 방사선 차폐용 시트상에 배치된 제2 접착층; 및상기 제2 접착층상에 배치된 제2 텍스타일;이 순차적으로 적층된 적층체를 포함하는 방사선 차폐용 텍스타일 복합체.
- 바닥면에 이형지를 포함하는 사이드 댐(side dam) 내부에 제17항에 따라 제조된 차폐용 조성물을 코팅하는 단계(단계 1);단계 1의 코팅된 조성물을 건조시켜 방사선 차폐용 시트를 제조하는 단계(단계 2); 및텍스타일을 상기 방사선 차폐용 시트와 접착하여 방사선 차폐용 텍스타일 복합체를 제조하는 단계(단계 3); 를포함하는 방사선 차폐용 텍스타일 복합체의 제조방법.
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KR102484194B1 (ko) * | 2020-12-23 | 2023-01-02 | 계명대학교 산학협력단 | 플라스틱 기반 방사선 차폐체의 제조방법, 그의 방사선 차폐체 및 그를 이용한 방사선 차폐장치 |
KR102496420B1 (ko) * | 2020-12-31 | 2023-02-06 | 동의대학교 산학협력단 | 라돈 차폐용 벽지 및 바닥재 |
CN113462041A (zh) * | 2021-07-20 | 2021-10-01 | 中国工程物理研究院材料研究所 | 一种防α辐射老化的橡胶制品及其制备方法 |
CN113674889B (zh) * | 2021-07-30 | 2023-11-14 | 海南大学 | 一种x射线辐射防护模块及其制造方法 |
CN114774014B (zh) * | 2022-03-18 | 2024-08-13 | 惠州东方雨虹建筑材料有限责任公司 | 一种无胎自粘防水卷材及其制备方法 |
KR102677296B1 (ko) * | 2022-04-27 | 2024-06-21 | 계명대학교 산학협력단 | 방사선 차폐 필름 및 이의 제조 방법 |
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- 2014-07-18 JP JP2016569983A patent/JP2017519205A/ja active Pending
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US20170200518A1 (en) | 2017-07-13 |
JP2017519205A (ja) | 2017-07-13 |
CN106415732A (zh) | 2017-02-15 |
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