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 multiple different types of material, such as boron carbide (B.sub.4C), steel, isotopically enriched boron carbide (.sup.10B.sub.4C), and blends thereof.

A feedthrough for shielding against a radioactive radiation, the feedthrough including: electrical feedthrough conductors; a tubular metal housing including ends and seals, the ends including a respective seals so that an interior is formed in the tubular housing between the seals, the seals including an insulating body through which an electrical feedthrough conductor is fed so that an electrical feedthrough conductor is fixed in the seals while being electrically insulated from the tubular housing; a connecting conductor extending in the interior, the connecting conductor connecting an electrical feedthrough conductor at one of the seals to an electrical feedthrough conductor at another of the seals; and shielding bodies, which are respectively interrupted by at least one opening therein, the shielding bodies being arranged successively in an axial direction of the tubular housing, the connecting conductor being fed through the opening.

A method for providing a neutron radiation shield includes a step (a) of providing a wall having an opening; and a step (b) of at least partially filling a space in the opening with a neutron moderator. Step (b) includes blast-injecting plastic granules into the opening with a blower device to form the neutron moderator.

A method for providing a neutron radiation shield includes a step (a) of providing a wall having an opening; and a step (b) of at least partially filling a space in the opening with a neutron moderator. Step (b) includes blast-injecting plastic granules into the opening with a blower device to form the neutron moderator.

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 method of generating power using a Thorium-containing molten salt fuel is disclosed. One example of the disclosed method includes the steps of providing a vessel containing a molten salt fuel, the molten salt fuel comprising Thorium and at least one salt containing a nucleus capable of interacting with a proton of sufficient energy to produce a (p, n) reaction resulting in the generation of a neutron at a first energy level and generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the at least one salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. In the example, the externally generated proton beam is directed into the vessel such that at least some protons forming the beam will interact with an atom forming a part of the at least one salt contained in the vessel to causing interaction between the externally generated proton beam and the at least one salt contained in the vessel to produce (p, n) reactions resulting in the generation of neutrons within the vessel and an absorption reaction involving the generated neutrons and Thorium within the vessel. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton’s interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases. the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.

Reactor buildings and vessel systems are disclosed. A nuclear power system includes: a building structure that comprises at least two exterior side walls and two end walls, at least one of the exterior walls angled non-orthogonally relative to a floor of the building structure, the at least two exterior walls and two end walls defining an interior volume of the building structure; one or more nuclear reactor systems mounted at least partially in the interior volume of the building structure; and one or more heat exchanger systems mounted at least partially to at least one of the exterior walls. A nuclear reactor vessel system includes: a nuclear fission reactor; an inner vessel that defines an inner volume sized to at least partially enclose the nuclear fission reactor; and an outer vessel sized to wholly or substantially enclose the inner vessel, the inner vessel being removable from the outer vessel.

A composite structure is disclosed comprising a neutron-absorbing metal hydride phase contained within a matrix having a density of greater than 95%. In various embodiments the metal hydride is a hydride of one or more of the following: Gadolinium, Hafnium, Europium, Samarium. The composite structure is utile as a shield for fusion or fission reactors.

A composite structure is disclosed comprising a neutron-absorbing metal hydride phase contained within a matrix having a density of greater than 95%. In various embodiments the metal hydride is a hydride of one or more of the following: Gadolinium, Hafnium, Europium, Samarium. The composite structure is utile as a shield for fusion or fission reactors.

A nuclear reactor facility may include a reactor building, a reactor vessel housed within the reactor building, and an auxiliary cooling system integrated with the reactor building. The reactor building has a visible section above a ground level and a buried section below the ground level. The reactor vessel contains a fuel core and is housed within the buried section of the reactor building below the ground level. The auxiliary cooling system includes a plurality of ducts integrated with the reactor building and is configured to passively cool the reactor vessel via natural air circulation.