A method for producing a lead-free X-ray shielding material using a bismuth halide compound is provided, the method including a first step of producing porous PDMS (Polydimethylsiloxane); a second step of producing a mixed solution of the bismuth halide compound and THF; and a third step of immersing the porous PDMS into the mixed solution such that the bismuth halide compound is loaded into the porous PDMS to produce a bismuth halide compound-PDMS composite material.

Systems and methods for left radial access, right room operation peripheral interventions are provided that include left radial bases to stabilize a left arm of a cardiac patient across a midsagittal plane, transradiant right radial bases to position a right arm of the patient, and radiodense radiation reduction barriers located between the patient and a doctor.

Systems and methods for left radial access, right room operation peripheral interventions are provided that include left radial bases to stabilize a left arm of a cardiac patient across a midsagittal plane, transradiant right radial bases to position a right arm of the patient, and radiodense radiation reduction barriers located between the patient and a doctor.

Certain exemplary embodiments can provide a system comprising a substantially transparent radiation shield, which comprises transparent ammonium metatungstate. The transparent ammonium metatungstate can have a density of greater than 1.5 gram/(cubic centimeter). The substantially transparent radiation shield can be installed on tanks and/or pressure vessels, used as a transparent radiation shield in medical shielding/devices, used as windows in glove boxes, and any application where effective radiation shielding is needed with transparency. The substantially transparent radiation shield can be used in one or more articles worn by a human.

Collimators and other components for use in neutron scattering experiments or to provide neutron shielding in nuclear reactors or accelerator based neutron sources are produced by additive manufacturing from neutron absorbing material, such as boron carbide (B.sub.4C) or isotopically enriched boron carbide (.sup.10B).

Conventional shielding materials are based on single material either toxic lead or barium based compounds and any matrix made therefrom contains only single phased barium based compounds, thereby posing limited radiation shielding capacity. Since brine sludge, an industrial toxic waste product, generated in chloralkali industry contains multiple compounds; there is a need to provide a process which enables the preparation of multi-phase based radiation shielding materials. In view of the above, the present invention provides advanced non-toxic radiation shielding materials utilizing tailored brine sludge and a process that enables conversion of toxic elements like chromium, zinc, copper and vanadium present in brine sludge into non-toxic shielding phases, thereby enabling to convert a toxic waste material into highly value added advanced radiation shielding materials possessing homogeneous radiation shielding matrix.

Conventional shielding materials are based on single material either toxic lead or barium based compounds and any matrix made therefrom contains only single phased barium based compounds, thereby posing limited radiation shielding capacity. Since brine sludge, an industrial toxic waste product, generated in chloralkali industry contains multiple compounds; there is a need to provide a process which enables the preparation of multi-phase based radiation shielding materials. In view of the above, the present invention provides advanced non-toxic radiation shielding materials utilizing tailored brine sludge and a process that enables conversion of toxic elements like chromium, zinc, copper and vanadium present in brine sludge into non-toxic shielding phases, thereby enabling to convert a toxic waste material into highly value added advanced radiation shielding materials possessing homogeneous radiation shielding matrix.

Collimators and other components for use in neutron scattering experiments or to provide neutron shielding in nuclear reactors or accelerator based neutron sources are produced by additive manufacturing from neutron absorbing material, such as boron carbide (B.sub.4C) or isotopically enriched boron carbide (.sup.10B).

Collimators and other components for use in neutron scattering experiments or to provide neutron shielding in nuclear reactors or accelerator based neutron sources are produced by additive manufacturing from neutron absorbing material, such as boron carbide (B.sub.4C) or isotopically enriched boron carbide (.sup.10B).

A neutron moderation material for use in a BNCT beam shaping assembly. The neutron moderation material comprises three elements, i.e., Mg, Al, and F, wherein the mass fraction of the Mg element is 3.5%-37.1%, the mass fraction of the Al element is 5%-90.4%, and the mass fraction of the F element is 5.8%-67.2%; the sum of the weights of the Mg, Al, and F elements is 100% of the total weight of the neutron moderation material. The neutron moderation material may be doped with a small amount of .sup.6Li-containing substances, and the addition of the .sup.6Li-containing substances effectively decreases the content of -rays in epithermal neutron beams.