Patent classifications
G21F1/042
Neutron Absorbing Concrete Wall and Method for Producing Such Concrete Wall
The object of the invention relates to a neutron absorbing concrete wall (10), which concrete wall (10) has an internal delimiting surface (11a), and an external delimiting surface (11b) on an opposite side to the internal delimiting surface (11a), the essence of which is that it contains a first concrete layer (13a) on the side of the internal delimiting surface (11a), and a second concrete layer (13b) on the side of the external delimiting surface (11b), which first concrete layer (13a) contains at least 0.05 mass % boron-10 isotope (10B), and the second concrete layer (13b) is formed as heavyweight concrete. The object of the invention also relates to a method for creating a neutron radiation absorbing concrete wall (10) that has an internal delimiting surface (11a), and an external delimiting surface (11b) on an opposite side to the internal delimiting surface (11a), the essence of which is a first concrete layer (13a) containing at least 0.05 mass % boron-10 isotope (.sup.10B) is formed on the side of the internal delimiting surface (11a), and a second concrete layer (13b) created as heavyweight concrete is formed on the side of the external delimiting surface (11b). The object of the invention also relates to a neutron absorbing concrete wall (10), the essence of which is that it is formed as heavyweight concrete containing at least 0.05 mass % boron-10 isotope (.sup.10B).
COMPOSITIONS, SYSTEMS, AND NEURAL NETWORKS FOR BIDIRECTIONAL ENERGY TRANSFER, AND THERMALLY ENHANCED SOLAR ABSORBERS
The present invention provides a bidirectional energy-transfer system comprising: a thermally and/or electrically conductive concrete, disposed in a structural object; a location of energy supply or demand that is physically isolated from, but in thermodynamic and/or electromagnetic communication with, the thermally and/or electrically conductive concrete; and a means of transferring energy between the structural object and the location of energy supply or demand. The system can be a single node in a neural network. The thermally and/or electrically conductive concrete includes a conductive, shock-absorbing material, such as graphite. Preferred compositions are disclosed for the thermally and/or electrically conductive concrete. The bidirectional energy-transfer system may be present in a solar-energy collection system, a grade beam, an indoor radiant flooring system, a structural wall or ceiling, a bridge, a roadway, a driveway, a parking lot, a commercial aviation runway, a military runway, a grain silo, or pavers, for example.
Mixture for anti-radiation pozzolon-polymeric cementitious material
An anti-radiation concrete comprising a geopolymer is described. In an implementation, the anti-radiation concrete comprises a mixture of at least two aqueous alkaline activators, fine aggregate, and coarse aggregate from high density metal-containing rocks.
Compositions and systems for bidirectional energy transfer and thermally enhanced solar absorbers
The present invention provides a bidirectional energy-transfer system comprising: a thermally and/or electrically conductive concrete, disposed in a structural object; a location of energy supply or demand that is physically isolated from, but in thermodynamic and/or electromagnetic communication with, the thermally and/or electrically conductive concrete; and a means of transferring energy between the structural object and the location of energy supply or demand. The system can be a single node in a neural network. The thermally and/or electrically conductive concrete includes a conductive, shock-absorbing material, such as graphite. Preferred compositions are disclosed for the thermally and/or electrically conductive concrete. The bidirectional energy-transfer system may be present in a solar-energy collection system, a grade beam, an indoor radiant flooring system, a structural wall or ceiling, a bridge, a roadway, a driveway, a parking lot, a commercial aviation runway, a military runway, a grain silo, or pavers, for example.
METHOD FOR PREPARING LOW-BACKGROUND CEMENT
A method for preparing low-background cement includes: uniformly mixing a seed crystal of cement, C.sub.4AF whiskers, and high-magnesium raw material to yield a first mixture, calcining the first mixture at 1400-1500 C., to yield a low-background clinker, the first mixture including 1.0-5.0 wt. % of the seed crystal of cement, 1.0-5.0 wt. % of the C.sub.4AF whiskers, and the balance is the high-magnesium raw material; and grinding a second mixture of the low-background clinker and gypsum, to yield low-background cement. The seed crystal of cement is a high-magnesium and low hydration heat clinker, has a specific activity of Ra-226 radioactive nuclides within 50 Bq/kg, and the MgO content of the clinker is between 4.0 wt. % and 5.0 wt. %, with 50 wt. % <C.sub.3S <55.0 wt. %; and the high-magnesium raw material has a MgO content between 2.5 wt. % and 3.0 wt. %.
Shielding material for shielding radioactive ray and preparation method thereof
A shielding material for shielding radioactive ray and preparation method thereof. The shielding material consists of water, a cementing material, a fine aggregate material, a coarse aggregate material and an additive, wherein the fine aggregate material consists of a borosilicate glass powder and a barite sand, and the coarse aggregate material consists of a barite. A content of boron element in the borosilicate glass powder accounts for 0.5%-1% of the total weight of the shielding material. A content of barium sulfate in the barite sand and the barite accounts for 71%-75% of the total weight of the shielding material. Other contents include water, the cementing material and the additive, and a sum of contents of all components is 100% total weight of the shielding material.
CEMENTITIOUS SHIELDING COMPOSITION FOR THE WIDE-SPECTRUM CAPTURE OF THERMAL, EPITHERMAL, AND FAST NEUTRONS
The present disclosure provides for cementitious shielding compositions, methods of making the cementitious shielding composition, structures incorporating the concrete cementitious shielding composition, and the like, where the cementitious shielding composition includes elemental boron and/or a boron compound, for example as boron particles. The boron particles can be homogeneously distributed throughout the cementitious shielding composition and can have a largest least dimension of about 100 microns or less. The present disclosure, in some aspects, can reduce or eliminate problems associated with minerals found in concrete aggregates, because those materials are degraded over time by neutron radiation, which leads to disorganized lattice structures, manifested as damage by radiation-induced volumetric expansion (RIVE), and potentially further damage from alkali-silica reaction (ASR).
RADIATION SHIELDING COMPOSITE MATERIAL
Radiation shielding composite material can include basalt fiber and concrete. The basalt fiber can be basalt-boron fiber, basalt-gadolinium fiber, basalt-boron gadolinium fiber, or a combination thereof. The concentration can be up to about 60 kilograms per cubic meter and, in some embodiments, range from about 60 kilograms per cubic meter to about 20 kilograms per cubic meter. The basalt fiber can be formed from a basalt melt that includes up to about 20% of boron oxide, up to about 20% of gadolinium oxide, and up to about 10% of boron oxide and about 10% of gadolinium oxide. The concrete can be ordinary concrete or heavy (i.e., barite) concrete.
NEUTRON CAPTURE THERAPY SYSTEM
A neutron capture therapy system is provided, including a neutron generating device and a beam shaping assembly. The neutron capture therapy system further includes a concrete wall forming a space for accommodating the neutron generating device and the beam shaping assembly and shielding radiations generated by the neutron generating device and the beam shaping assembly. A support module is disposed in the concrete wall, the support module is capable of supporting the beam shaping assembly and is used to adjust the position of the beam shaping assembly, and the support module includes concrete and a reinforcing portion at least partially disposed in the concrete. The neutron capture therapy system designs a locally adjustable support for the beam shaping assembly, so that the beam shaping assembly can meet the precision requirement, improve the beam quality, and meet an assembly tolerance of the target.
Method for preparing low-background cement
A method for preparing low-background cement includes: uniformly mixing a seed crystal of cement, C.sub.4AF whiskers, and high-magnesium raw material to yield a first mixture, calcining the first mixture at 1400-1500? C., to yield a low-background clinker, the first mixture including 1.0-5.0 wt. % of the seed crystal of cement, 1.0-5.0 wt. % of the C.sub.4AF whiskers, and the balance is the high-magnesium raw material; and grinding a second mixture of the low-background clinker and gypsum, to yield low-background cement. The seed crystal of cement is a high-magnesium and low hydration heat clinker, has a specific activity of Ra-226 radioactive nuclides within 50 Bq/kg, and the MgO content of the clinker is between 4.0 wt. % and 5.0 wt. %, with 50 wt. %?C.sub.3S?55.0 wt. %; and the high-magnesium raw material has a MgO content between 2.5 wt. % and 3.0 wt. %.