The present invention relates to a lead free glossy finish hybrid radiation shielding composite panel comprising: a) 40-70% of industrial waste red mud and 30-60% of epoxy/polyester resin with or without glass fibre, wherein the composite panel has density in the range of 1.4-2.2 g/cc; water absorption in the range of 0.20-0.30%; tensile strength in the range of 12-120 MPa; tensile modulus in the range of 1.5-7.5 GPa; and half value layer in the range of 0.36-0.47 cm and 0.48-0.52 cm for X-ray beam energies of 60 and 100 kVp, respectively. The present invention also describes a low temperature process for manufacturing the composite panels. Moreover, the developed composite panel is a unique material and have multifunctional applications in wider spectrum as high energy electromagnetic radiation shielding doors, panels, partition panels and as roofing sheets.

Described herein are methods of forming a neutron shielding material. Such material may comprise a powder blend comprising a first component comprising a blend of a first metal particle and a first ceramic particle; and a second component comprising a reinforcing chip, the reinforcing chip comprising a second ceramic particle dispersed within a chip metal matrix.

A radiation shield unit, which shields against neutron rays, X-rays, and γ-rays, contains 10 vol % or more and 90 vol % or less of gadolinium.

A radiation-shielding attenuation structure and method of forming the attenuation structure, wherein the attenuation structure is made by additively manufacturing a concrete material that includes one or more attenuation dopants configured to enhance the radiation shielding of the concrete material. The one or more attenuation dopants may be configured in the concrete material to attenuate one or more types of radiation, such as electromagnetic radiation, gamma radiation, X-ray radiation, or neutron radiation. The attenuation structure formed by the concrete material may be additively manufactured on-site according to a model that has already been pre-certified for safe or secure use, thereby providing a repeatable and reproducible process that can reduce lead times and fabrication costs. The attenuation structure may be easily modified during the additive manufacturing process to have different concrete mixtures with different attenuation characteristics, which increases the tailorability and flexibility in design of the attenuation structure.

Described herein are methods of forming a neutron shielding material. Such material may comprise a powder blend comprising a first component comprising a blend of a first metal particle and a first ceramic particle; and a second component comprising a reinforcing chip, the reinforcing chip comprising a second ceramic particle dispersed within a chip metal matrix.

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).

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).

Described herein are methods of forming a neutron shielding material. Such material may comprise a powder blend comprising a first component comprising a blend of a first metal particle and a first ceramic particle; and a second component comprising a reinforcing chip, the reinforcing chip comprising a second ceramic particle dispersed within a chip metal matrix.

Described herein is a powder blend comprising a first component comprising a blend of a first metal particle and a first ceramic particle; and a second component comprising a reinforcing chip, the reinforcing chip comprising a second ceramic particle dispersed within a chip metal matrix.

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.