The present invention relates to a low-activation concrete comprising high-purity limestone aggregate and white cement, or high-purity limestone aggregate and aluminous cement. The low-activation concrete reduces the content of Europium, Cobalt and Cesium, as well as the content of elements such as Aluminium, Sodium, and Magnesium, when compared to standard concrete compositions and compositions for low-activation concrete already known in the art. The use of the low-activation concrete for forming an interior wall of a particle accelerator vault is provided as well.

The novel process enables designing of raw materials and processing parameters, enabling synergistic and simultaneous chemical reactions among the various reactants of the design mix of chemical precursor of brine sludge which includes barium sulphate, magnesium hydroxide, calcium carbonate, sodium chloride, silica, aluminum containing compounds necessary for developing highly efficient shielding phases leading to homogenous matrix of shielding materials.

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.

A multi-functional polymer concrete using polymer or cement-polymer binders modified with boron nanotubes and heavyweight aggregate particles.

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 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.

The present disclosure, in an embodiment, is a facility that includes a device configured to generate a beam having an energy range of 5 MeV to 500 MeV, a first radiation shielding wall surrounding the device, a second radiation shielding wall surrounding the first radiation shielding wall, radiation shielding fill material positioned between the first radiation shielding wall and the second radiation shielding wall forming a first barrier. In embodiments, the radiation shielding fill material includes at least fifty percent by weight of an element having an atomic number from 12 to 83, and a thickness of the first barrier is 0.5 meter to 6 meters.

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 self-supporting inorganic and radiation-hard neutron shielding panel for use in absorbing thermal neutrons. The panel is constructed substantially of concrete and includes a high level of boron by weight to enhance the absorption of thermal neutrons. A layer of radiation-resistant fiber reinforcement within the panel enables production of a thin, strong panel that is self-supporting and easily transportable. Mounting means are included on the panel to facilitate easy mounting on a wall or similar surface. The panels are constructed entirely of inorganic materials and include at least 58% boron by weight to maximize their effectiveness in shielding against thermal neutrons. Further disclosed are methods for forming the neutron-shielding panels.

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.