US20100090168A1 - Radiation shielding structure composition - Google Patents
Radiation shielding structure composition Download PDFInfo
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- US20100090168A1 US20100090168A1 US12/572,795 US57279509A US2010090168A1 US 20100090168 A1 US20100090168 A1 US 20100090168A1 US 57279509 A US57279509 A US 57279509A US 2010090168 A1 US2010090168 A1 US 2010090168A1
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- acid phosphate
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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
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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
- C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
- C04B28/34—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing cold phosphate binders
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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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
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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
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00241—Physical properties of the materials not provided for elsewhere in C04B2111/00
- C04B2111/00258—Electromagnetic wave absorbing or shielding materials
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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
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00474—Uses not provided for elsewhere in C04B2111/00
- C04B2111/00862—Uses not provided for elsewhere in C04B2111/00 for nuclear applications, e.g. ray-absorbing concrete
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
- Y02W30/91—Use of waste materials as fillers for mortars or concrete
Definitions
- the present invention relates generally to a composition useful in radiation shielding applications.
- radiation shielding structures are common, particularly in the nuclear technology field and in any radiation producing facility.
- Exemplary radiation sources include cosmic rays, x-rays in medical facilities, nuclear reactors, cathode ray tubes (e.g. TV and computer monitors) and the like. Radiation doses are carefully monitored in a wide variety of settings, and there are a number of regulatory standards for human exposure levels. Radiation shielding is also important for limiting exposure of sensitive equipment to radiation. For example, protection of a nuclear reaction vessel from gamma rays. Another example, is the protection of other medical devices from radiation from a medial device that emits radiation.
- U.S. Pat. No. 5,786,611 proposes containers for storing spent nuclear wastes.
- the containers comprise concrete with stable uranium oxide aggregate and a neutron absorbing material such as B 7 O 3 , HfO 3 or Gd 2 O 3 .
- U.S. Pat. No. 4,727,257 proposes a radiation shielding composition comprising an aggregate-containing cement based mortar wherein the aggregate comprises floated gelata and a boron mineral.
- a phosphate ceramic radiation shielding composition comprises a magnesium, potassium and phosphorous binder, and means for dissipating heat such as B 4 C, Bi 2 O 3 , Fe 2 O 3 , Fe 3 O 4 , Pb metal and lead.
- compositions for radiation shielding structures which are less expensive and less dependent on heavy metals while providing acceptable levels of shielding from radiation.
- Radiation shielding structures are widely used for shielding of nuclear power plants, particle accelerators, research reactors, laboratory equipment, and radiation and x-ray medical facilities.
- An important aspect is selecting the specific shielding structure as the required attenuation coefficient or reduction factor.
- the Linear Attenuation Coefficient ( ⁇ ) is dependent on the density of the shielding material. To obviate the effects of variations in the density of a material, the linear attenuation coefficient is expressed as a mass attenuation coefficient ( ⁇ / ⁇ ) cm 2 g ⁇ 1 . It is the direct measure of the effectiveness of a shielding material based upon unit mass of a material.
- the present invention provides a radiation shielding structure composition comprising calcium silicate, magnesium oxide and an acid phosphate.
- the radiation shielding structure has an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 ⁇ Ci Cs-137 source) and 1.173 MeV (1 ⁇ Ci Co-60 source).
- the present invention provides a radiation shielding structure composition
- a radiation shielding structure composition comprising magnesium or calcium oxide, an acid phosphate and fly ash and having an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 ⁇ Ci Cs-137 source) and 1.173 MeV (1 ⁇ Ci Co-60 source).
- the present invention provides a radiation curing structure composition
- a radiation curing structure composition comprising magnesium or calcium oxide, an acid phosphate and kaolin and having an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 ⁇ Ci Cs-137 source) and 1.173 MeV (1 ⁇ Ci Co-60 source).
- FIG. 1 is a graph of attenuation coefficients for the radiation shielding structure compositions of Examples 1-6 and ordinary concrete (“OC”) for 0.666 MeV photon energy using a 5 mCi Cs-137 source.
- FIG. 2 is a graph of attenuation coefficients for the radiation shielding structure compositions of Examples 1-6 and ordinary concrete (“OC”) for 1.173 MeV photon energy using a 1 ⁇ Ci Co-60 source.
- the radiation shielding structure comprises calcium silicate (wollastonite), magnesium oxide and an acid phosphate.
- the composition comprises about 15 to 40 percent by weight calcium silicate, about 10 to 35 percent by weight magnesium oxide and about 25 to 45 percent by weight acid phosphate.
- Such a composition optionally may include kaolin or fly ash at a 0.1 to 40 percent by weight level.
- the radiation shielding structure comprises magnesium or calcium oxide, an acid phosphate and fly ash. In one embodiment, the structure comprises 15 to 40 percent by weight calcined magnesium or calcium oxide, 25 to 55 percent by weight acid phosphate and 20 to 40 percent by weight fly ash.
- the radiation shielding structure comprises a magnesium or calcium oxide, an acid phosphate and kaolin.
- the structure comprises 15 to 40 percent by weight calcined magnesium or calcium oxide, 20 to 55 percent by weight acid phosphate and 5 to 25 percent by weight kaolin
- Exemplary acid phosphates include monopotassium phosphate, magnesium phosphate, sodium phosphate, aluminum phosphate, ammonium phosphate, iron phosphate, zinc phosphate, and combinations thereof.
- the acid phosphate may be monopotassium phosphate.
- Suitable additives may be mixed with the radiation shielding structure composition and typically the amounts added may be from about 0.1 to about 30 percent by weight.
- Exemplary additives include flame retardants, vermiculite, perlite, fibers, emulsifiers, deflocculates, sequestrates, granular additives, coarse aggregates such as stone and sand, chemical additives such as boric acid, accelerators (e.g., Accelguard available from The Euclid Chemical Company, Cleveland, Ohio) colorants and pigments, fillers, aggregates, borax, silica materials, iron oxides, bonding adhesives (e.g., Eucopoxy Resin and Eucoweld available from The Euclid Chemical Company, Cleveland, Ohio, Flexcon, and Corr-bond) plasticizers, hardeners (e.g., Euco Diamond Hard available from The Euclid Chemical Company, Cleveland, Ohio), patching polymers (e.g., Eucorapid patch available from The Euclid Chemical Company, Cleveland, Ohio), micro silica fume (e.
- neutron absorbers also may be added to the radiation shielding structure.
- exemplary neutron absorbers include heavy metals and heavy metal compounds such as boron, B 2 O 3 , HfO 3 , Gd 2 O 3 , iron oxides, lead, and the like.
- various reinforcement may be included in the composition or the composition may be applied to the reinforcement.
- Exemplary reinforcement includes steel (e.g. rebar), other metals (e.g., lead) carbon, glass, stone, basalt, and the like in fiber, particulate and/or fabric/mat form.
- the radiation shielding structure composition can be mixed as a slurry and sprayed on an existing surface or substrate to improve the attenuation coefficient of that surface or the slurry can be sprayed, extruded, molded, and the like into a predetermined shape.
- Suitable structures include shielding for nuclear power plants, particle accelerators, research reactors, x-ray equipment, radiation equipment, and the like.
- Other structures include transport and storage vessels for containing waste capable of emitting harmful radiation such as described in U.S. Ser. No. ______, filed Oct. 2, 2009 [Attorney Docket No. 9591-8], the disclosure of which is incorporated herein by reference in its entirety.
- Examples 1-6 were formulated as follows:
- Example 1 was repeated with salt water.
- the sample tested had a thickness of 2.00 inches.
- Example 1 was repeated and the sample tested had a thickness of 1.00 inches. The testing was conducted using a method for measuring attenuation coefficients developed by North Carolina State University.
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- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Physics & Mathematics (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Inorganic Chemistry (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
- Environmental & Geological Engineering (AREA)
- Curing Cements, Concrete, And Artificial Stone (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
Radiation structures formed from a composition including calcium silicate, magnesium or calcium oxides and an acid phosphate are provided. The composition may also include fly ash or kaolin with or without the calcium silicate.
Description
- This application claims priority to U.S. Provisional Application Ser. No. 61/102,997, filed Oct. 6, 2008, the contents of which are hereby incorporated by reference as if recited in full herein.
- The present invention relates generally to a composition useful in radiation shielding applications.
- The use of radiation shielding structures is common, particularly in the nuclear technology field and in any radiation producing facility. Exemplary radiation sources include cosmic rays, x-rays in medical facilities, nuclear reactors, cathode ray tubes (e.g. TV and computer monitors) and the like. Radiation doses are carefully monitored in a wide variety of settings, and there are a number of regulatory standards for human exposure levels. Radiation shielding is also important for limiting exposure of sensitive equipment to radiation. For example, protection of a nuclear reaction vessel from gamma rays. Another example, is the protection of other medical devices from radiation from a medial device that emits radiation.
- Concrete or cement is often a candidate material for use in radiation shielding. For example, U.S. Pat. No. 5,786,611 proposes containers for storing spent nuclear wastes. The containers comprise concrete with stable uranium oxide aggregate and a neutron absorbing material such as B7O3, HfO3 or Gd2O3. U.S. Pat. No. 4,727,257 proposes a radiation shielding composition comprising an aggregate-containing cement based mortar wherein the aggregate comprises floated gelata and a boron mineral. U.S. Publication No. 2002/0165082 proposes a phosphate ceramic radiation shielding composition comprises a magnesium, potassium and phosphorous binder, and means for dissipating heat such as B4C, Bi2O3, Fe2O3, Fe3O4, Pb metal and lead.
- There is, however, a need for compositions for radiation shielding structures which are less expensive and less dependent on heavy metals while providing acceptable levels of shielding from radiation.
- Radiation shielding structures are widely used for shielding of nuclear power plants, particle accelerators, research reactors, laboratory equipment, and radiation and x-ray medical facilities. An important aspect is selecting the specific shielding structure as the required attenuation coefficient or reduction factor. The Linear Attenuation Coefficient (μ) is dependent on the density of the shielding material. To obviate the effects of variations in the density of a material, the linear attenuation coefficient is expressed as a mass attenuation coefficient (μ/ρ) cm2g−1. It is the direct measure of the effectiveness of a shielding material based upon unit mass of a material.
- To this end, the present invention provides a radiation shielding structure composition comprising calcium silicate, magnesium oxide and an acid phosphate. The radiation shielding structure has an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 μCi Cs-137 source) and 1.173 MeV (1 μCi Co-60 source).
- In another embodiment, the present invention provides a radiation shielding structure composition comprising magnesium or calcium oxide, an acid phosphate and fly ash and having an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 μCi Cs-137 source) and 1.173 MeV (1 μCi Co-60 source).
- In still another embodiment, the present invention provides a radiation curing structure composition comprising magnesium or calcium oxide, an acid phosphate and kaolin and having an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 μCi Cs-137 source) and 1.173 MeV (1 μCi Co-60 source).
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FIG. 1 is a graph of attenuation coefficients for the radiation shielding structure compositions of Examples 1-6 and ordinary concrete (“OC”) for 0.666 MeV photon energy using a 5 mCi Cs-137 source. -
FIG. 2 is a graph of attenuation coefficients for the radiation shielding structure compositions of Examples 1-6 and ordinary concrete (“OC”) for 1.173 MeV photon energy using a 1 μCi Co-60 source. - The foregoing and other aspects of the present invention will now be described in more detail with respect to other embodiments described herein. It should be appreciated that the invention can be embodied in different forms and should not be construed as limited to the embodiments set forth herein. Rather, these embodiments are provided so that this disclosure will be thorough and complete, and will fully convey the scope of the invention to those skilled in the art.
- The terminology used in the description of the invention herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention. As used in the description of the embodiments of the invention and the appended claims, the singular forms “a”, “an” and “the” are intended to include the plural forms as well, unless the context clearly indicates otherwise. Also, as used herein, “and/or” refers to and encompasses any and all possible combinations of one or more of the associated listed items. Furthermore, the term “about,” as used herein when referring to a measurable value such as an amount of a compound, dose, time, temperature, and the like, is meant to encompass variations of 20 percent, 10 percent, 5 percent, 1 percent, 0.5 percent, or even 0.1 percent of the specified amount. Unless otherwise defined, all terms, including technical and scientific terms used in the description, have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs.
- The radiation shielding structure comprises calcium silicate (wollastonite), magnesium oxide and an acid phosphate. In one embodiment, the composition comprises about 15 to 40 percent by weight calcium silicate, about 10 to 35 percent by weight magnesium oxide and about 25 to 45 percent by weight acid phosphate. Such a composition optionally may include kaolin or fly ash at a 0.1 to 40 percent by weight level.
- In another embodiment the radiation shielding structure comprises magnesium or calcium oxide, an acid phosphate and fly ash. In one embodiment, the structure comprises 15 to 40 percent by weight calcined magnesium or calcium oxide, 25 to 55 percent by weight acid phosphate and 20 to 40 percent by weight fly ash.
- In another embodiment, the radiation shielding structure comprises a magnesium or calcium oxide, an acid phosphate and kaolin. In one embodiment, the structure comprises 15 to 40 percent by weight calcined magnesium or calcium oxide, 20 to 55 percent by weight acid phosphate and 5 to 25 percent by weight kaolin
- Exemplary acid phosphates include monopotassium phosphate, magnesium phosphate, sodium phosphate, aluminum phosphate, ammonium phosphate, iron phosphate, zinc phosphate, and combinations thereof. In the embodiments above, the acid phosphate may be monopotassium phosphate.
- Suitable additives may be mixed with the radiation shielding structure composition and typically the amounts added may be from about 0.1 to about 30 percent by weight. Exemplary additives include flame retardants, vermiculite, perlite, fibers, emulsifiers, deflocculates, sequestrates, granular additives, coarse aggregates such as stone and sand, chemical additives such as boric acid, accelerators (e.g., Accelguard available from The Euclid Chemical Company, Cleveland, Ohio) colorants and pigments, fillers, aggregates, borax, silica materials, iron oxides, bonding adhesives (e.g., Eucopoxy Resin and Eucoweld available from The Euclid Chemical Company, Cleveland, Ohio, Flexcon, and Corr-bond) plasticizers, hardeners (e.g., Euco Diamond Hard available from The Euclid Chemical Company, Cleveland, Ohio), patching polymers (e.g., Eucorapid patch available from The Euclid Chemical Company, Cleveland, Ohio), micro silica fume (e.g., Eucoshot available from The Euclid Chemical Company, Cleveland, Ohio), setting retarders, surface softeners, and kaolins, curing compounds (e.g., Brownstone CS), water reducers (e.g., Accelguard, Eucon AC), and air entrainers (e.g., AEA and Air Mix).
- Alternatively, neutron absorbers also may be added to the radiation shielding structure. Exemplary neutron absorbers include heavy metals and heavy metal compounds such as boron, B2O3, HfO3, Gd2O3, iron oxides, lead, and the like.
- Alternatively, various reinforcement may be included in the composition or the composition may be applied to the reinforcement. Exemplary reinforcement includes steel (e.g. rebar), other metals (e.g., lead) carbon, glass, stone, basalt, and the like in fiber, particulate and/or fabric/mat form.
- The radiation shielding structure composition can be mixed as a slurry and sprayed on an existing surface or substrate to improve the attenuation coefficient of that surface or the slurry can be sprayed, extruded, molded, and the like into a predetermined shape. Suitable structures include shielding for nuclear power plants, particle accelerators, research reactors, x-ray equipment, radiation equipment, and the like. Other structures include transport and storage vessels for containing waste capable of emitting harmful radiation such as described in U.S. Ser. No. ______, filed Oct. 2, 2009 [Attorney Docket No. 9591-8], the disclosure of which is incorporated herein by reference in its entirety.
- The following examples are merely illustrative of the invention, and are not limiting thereon.
- Examples 1-6 were formulated as follows:
-
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Magnesium Oxide 23% Monopotassium Phosphate 23% Fly Ash 21% Sand 33%
The sample tested had a thickness of 0.50 inches. -
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Magnesium Oxide 20% Monopotassium Phosphate 23% Calcium Silicate 24% Sand 33%
The sample tested had a thickness of 1.25 inches. - Example 1 was repeated with salt water. The sample tested had a thickness of 2.00 inches.
-
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Magnesium Oxide 23% Monopotassium Phosphate 23% Fly Ash 11% Kaolin 10% Sand 33%
The sample tested had a thickness of 0.75 inches. -
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Magnesium Oxide 30% Monopotassium Phosphate 34% Calcium Silicate 36%
The sample tested had a thickness of 0.50 inches. -
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Magnesium Oxide 30% Monopotassium Phosphate 31% Fly Ash 28% Sodium Bicarbonate 10%
The sample tested had a thickness of 1.00 inches. - Example 1 was repeated and the sample tested had a thickness of 1.00 inches. The testing was conducted using a method for measuring attenuation coefficients developed by North Carolina State University.
- As can be seen from
FIGS. 1 and 2 , the formulations for Examples 1-6 have significantly improved attenuation coefficients as compared to ordinary concrete. - A formulation as follows was prepared.
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Magnesium Oxide 34% Monopotassium Phosphate 31% Fly Ash 17% Kaolin 15% -
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Magnesium Oxide 34% Monopotassium Phosphate 31% Fly Ash 17% Kaolin 15% Sand 30% - Having thus described certain embodiments of the present invention, it is to be understood that the invention defined by the appended claims is not to be limited by particular details set forth in the above description as many apparent variations thereof are possible without departing from the spirit or scope thereof as hereinafter claimed.
Claims (18)
1. A radiation shielding structure composition comprising calcium silicate, magnesium oxide and an acid phosphate and having an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 μCi Cs-137 source) and 1.173 MeV (1 μCi Co-60 source).
2. The radiation shielding structure composition of claim 1 comprising 10 to 40 percent by weight calcium silicate, 10 to 35 percent by weight magnesium oxide and 15 to 45 percent by weight acid phosphate.
3. The radiation shielding structure composition of claim 2 , wherein the acid phosphate is monopotassium phosphate.
4. A radiation shielding structure comprising the radiation shielding structure composition of claim 1 sprayed onto a substrate or formed into predetermined structure.
5. A radiation shielding structure composition comprising a magnesium or calcium oxide, an acid phosphate and fly ash and having an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 μCi Cs-137 source) and 1.173 MeV (1 μCi Co-60 source).
6. The radiation shielding structure composition of claim 5 comprising 15 to 35 percent by weight calcined magnesium or calcium oxide, 15 to 55 percent by weight acid phosphate and 20 to 40 percent by weight fly ash.
7. The radiation shielding structure composition of claim 6 , wherein the acid phosphate is monopotassium phosphate.
8. A radiation shielding structure comprising the radiation shielding structure composition of claim 5 sprayed onto a substrate or formed into predetermined structure.
9. A radiation curing structure composition comprising magnesium or calcium oxide, an acid phosphate and kaolin and having an improved attenuation coefficient as compared to ordinary concrete based on photon energies of 0.662 MeV (5 μCi Cs-137 source) and 1.173 MeV (1 μCi Co-60 source).
10. The radiation shielding structure composition of claim 5 comprising 15 to 35 percent by weight calcined magnesium or calcium oxide, 15 to 55 percent by weight acid phosphate and 20 to 40 percent by weight kaolin.
11. The radiation shielding structure composition of claim 10 , wherein the acid phosphate is monopotassium phosphate.
12. A radiation shielding structure comprising the radiation shielding structure composition of claim 10 sprayed onto a substrate or formed into predetermined structure.
13. A method of shielding a structure or substrate from radiation, the method comprising applying a composition comprising calcium silicate, magnesium oxide and an acid phosphate to the structure or substrate.
14. The phosphate method of claim 13 , wherein the composition comprises 10 to 40 percent by weight calcium silicate, 10 to 35 percent by weight magnesium oxide and 15 to 45 percent by weight acid phosphate.
15. A method of shielding a structure or substrate from radiation, the method comprising applying a composition comprising magnesium or calcium oxide, an acid phosphate and fly ash to the structure or substrate.
16. The method of claim 15 , wherein the composition comprises 15 to 40 percent by weight calcined magnesium or calcium oxide, 15 to 55 percent by weight acid phosphate and 20 to 40 percent by weight fly ash.
17. A method of shielding a structure or substrate from radiation, the method comprising applying a composition comprising magnesium or calcium oxide, an acid phosphate and kaolin to the structure or substrate.
18. The method of claim 17 , wherein the composition comprises 15 to 40 percent by weight calcined magnesium or calcium oxide, 15 to 55 percent by weight acid phosphate and 20 to 40 percent by weight kaolin.
Priority Applications (10)
Application Number | Priority Date | Filing Date | Title |
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US12/572,795 US20100090168A1 (en) | 2008-10-06 | 2009-10-02 | Radiation shielding structure composition |
EP09819697A EP2345042A4 (en) | 2008-10-06 | 2009-10-05 | Radiation shielding structure composition |
KR20117010297A KR20110084416A (en) | 2008-10-06 | 2009-10-05 | Radiation shielding structure composition |
CA 2742259 CA2742259A1 (en) | 2008-10-06 | 2009-10-05 | Radiation shielding structure composition |
CN2009801488274A CN102246245A (en) | 2008-10-06 | 2009-10-05 | Radiation shielding structure composition |
BRPI0920603A BRPI0920603A2 (en) | 2008-10-06 | 2009-10-05 | composed of radiation shielding structure, and radiation curing structure, radiation shielding structure, and method of shielding a radiation structure or substrate. |
PCT/US2009/059476 WO2010042416A2 (en) | 2008-10-06 | 2009-10-05 | Radiation shielding structure composition |
JP2011531088A JP2012504773A (en) | 2008-10-06 | 2009-10-05 | Composition for radiation shielding structure |
TW98133871A TW201019348A (en) | 2008-10-06 | 2009-10-06 | Radiation shielding structure composition |
US13/715,058 US20140061542A1 (en) | 2008-10-06 | 2012-12-14 | Radiation shielding structure composition |
Applications Claiming Priority (2)
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US10299708P | 2008-10-06 | 2008-10-06 | |
US12/572,795 US20100090168A1 (en) | 2008-10-06 | 2009-10-02 | Radiation shielding structure composition |
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US13/715,058 Continuation US20140061542A1 (en) | 2008-10-06 | 2012-12-14 | Radiation shielding structure composition |
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US20100090168A1 true US20100090168A1 (en) | 2010-04-15 |
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US12/572,795 Abandoned US20100090168A1 (en) | 2008-10-06 | 2009-10-02 | Radiation shielding structure composition |
US12/572,812 Expired - Fee Related US8409346B2 (en) | 2008-10-06 | 2009-10-02 | Waste storage vessels and compositions therefor |
US13/715,058 Abandoned US20140061542A1 (en) | 2008-10-06 | 2012-12-14 | Radiation shielding structure composition |
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US12/572,812 Expired - Fee Related US8409346B2 (en) | 2008-10-06 | 2009-10-02 | Waste storage vessels and compositions therefor |
US13/715,058 Abandoned US20140061542A1 (en) | 2008-10-06 | 2012-12-14 | Radiation shielding structure composition |
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US (3) | US20100090168A1 (en) |
EP (2) | EP2345042A4 (en) |
JP (2) | JP2012504774A (en) |
KR (2) | KR20110084417A (en) |
CN (2) | CN102246244A (en) |
BR (2) | BRPI0920813A2 (en) |
CA (2) | CA2742305A1 (en) |
TW (2) | TW201019348A (en) |
WO (2) | WO2010042417A2 (en) |
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Also Published As
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BRPI0920813A2 (en) | 2017-07-11 |
EP2345042A4 (en) | 2012-06-27 |
US8409346B2 (en) | 2013-04-02 |
BRPI0920603A2 (en) | 2015-12-22 |
KR20110084416A (en) | 2011-07-22 |
JP2012504773A (en) | 2012-02-23 |
TW201019347A (en) | 2010-05-16 |
TW201019348A (en) | 2010-05-16 |
WO2010042417A3 (en) | 2010-07-08 |
EP2345042A2 (en) | 2011-07-20 |
CN102246245A (en) | 2011-11-16 |
JP2012504774A (en) | 2012-02-23 |
WO2010042416A2 (en) | 2010-04-15 |
KR20110084417A (en) | 2011-07-22 |
EP2345043A2 (en) | 2011-07-20 |
WO2010042417A2 (en) | 2010-04-15 |
EP2345043A4 (en) | 2012-06-20 |
CN102246244A (en) | 2011-11-16 |
US20140061542A1 (en) | 2014-03-06 |
CA2742305A1 (en) | 2010-04-15 |
CA2742259A1 (en) | 2010-04-15 |
WO2010042416A3 (en) | 2010-07-08 |
US20100089292A1 (en) | 2010-04-15 |
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