A radiation attenuation shield, method, and system are disclosed. The shield includes a polymer, a radiation attenuating material, and a magnetic material. The radiation attenuating material and the magnetic material may be dispersed within the polymer to form an attenuation layer. Further, a magnetic material layer may be positioned adjacent to the attenuation layer or encase the attenuation layer. The radiation attenuation shield may be made by combining the components to create a mixture and then inserting the mixture in a mold until a solidified shape is formed. Moreover, the radiation attenuation shield of the present invention may be mechanically secured to a structure to contain radiation. Further, the shield may be secured to a structure by using the magnetic properties of the shield.

A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as one or more layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. The gaseous fission products can be withdrawn from the irradiation chamber on a continuous basis, and the radioactive iodine isotopes (including I-131) extracted.

A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as one or more layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. The gaseous fission products can be withdrawn from the irradiation chamber on a continuous basis, and the radioactive iodine isotopes (including I-131) extracted.

A method of fabricating a polycrystalline crystal of a radiation sensitive material used for radiation detectors or shielding includes providing constituent powders or a single crystal material of the radiation sensitive material or a mixed combination thereof, forming a single phase powder of the radiation sensitive material via solid-state thermochemical and/or thermomechanical reaction between constituent powders or milling the single crystal material of the radiation sensitive material into powders, and pressing the single phase powder of the radiation sensitive material via Field Assisted Sintering Technology to form a pellet, component or structure of the polycrystalline radiation sensitive material.

The present invention provides a composition for material comprising brine sludge waste and a process for the preparation thereof process for preparation of flexible, functional, and moldable material using advanced Chem-heat treated brine sludge-based composition via solvent-free route for developing samples of various dimensions. The present invention involves developing desired, suitable, and appropriate phases possessing uniform and homogenous matrix in the developed material. Thus, designing molecular moieties in the developed process leads to forming tightly bound three-dimensional structures, strengthening the developed advanced chemically designed material which is cost-effective, non-toxic, highly versatile (can be bent or shaped to fit around curves and corners), durable, easy to install, safe with superior performance and economically feasible advanced flexible, functional and moldable material with a homogeneous uniform matrix using advanced dual chem-heat treated brine sludge based composition for a broad application spectrum.

The present invention provides: a curable composition which contains a bismuth compound, wherein a phosphoric acid ester having a (meth)acryloyl group is bonded to bismuth, and a nitrile compound having a radically polymerizable carbon-carbon double bond; a cured body which is obtained by curing this curable composition; a multilayer body which is composed of the above-described cured body and a cured body that is obtained by curing a photochromic curable composition; and a radiation protective material which is formed of the above-described cured body or the above-described multilayer body.