Abstract: Neutron shielding comprising a metal-hydride metal composite: the metal-hydride metal composite comprising: a metal matrix; and a plurality of metal-hydride particles dispersed within the metal matrix; wherein, the fraction of metal-hydride in the metal-hydride metal composite is at least 1 mol % and the volume fraction of metal-hydride in the metal hydride metal composite is no higher than the ratio of the solid solubility limit of hydrogen in the metal matrix and the molar fraction of hydrogen in the metal-hydride.

Abstract: Neutron shielding. The neutron shielding comprises a plurality of absorption layers, and at least one moderating layer. The plurality of absorption layers each comprise tungsten boride or tungsten carbide. The at least one moderating layer comprises a metal hydride. Each moderating layer is between at least two absorption layers.

Abstract: Neutron shielding. The neutron shielding comprises a plurality of absorption layers (201, 203), and at least one moderating layer (202). The plurality of absorption layers each comprise tungsten boride or tungsten carbide. The at least one moderating layer comprises a metal hydride. Each moderating layer is between at least two absorption layers.

Abstract: Neutron shielding comprising a metal-hydride metal composite: the metal-hydride metal composite comprising: a metal matrix; and a plurality of metal-hydride particles dispersed within the metal matrix; wherein, the fraction of metal-hydride in the metal-hydride metal composite is at least 1 mol % and the volume fraction of metal-hydride in the metal hydride metal composite is no higher than the ratio of the solid solubility limit of hydrogen in the metal matrix and the molar fraction of hydrogen in the metal-hydride.

Abstract: A breeder blanket for generating tritium using neutrons produced by nuclear fusion of deuterium and/or tritium within a plasma confined within a fusion reactor. The breeder blanket comprises: a plasma-facing first wall; a breeder layer comprising lithium containing material for generating tritium from the neutrons; and neutron moderator material comprising metal hydride and/or deuteride arranged between the first wall and the lithium-containing material.

Abstract: A breeder blanket for generating tritium using neutrons produced by nuclear fusion of deuterium and/or tritium within a plasma confined within a fusion reactor. The breeder blanket comprises: a plasma-facing first wall; a breeder layer comprising lithium containing material for generating tritium from the neutrons; and neutron moderator material comprising metal hydride and/or deuteride arranged between the first wall and the lithium-containing material.

Abstract: Neutron shielding. The neutron shielding comprises a plurality of absorption layers (201, 203), and at least one moderating layer (202). The plurality of absorption layers each comprise tungsten boride or tungsten carbide. The at least one moderating layer comprises a metal hydride. Each moderating layer is between at least two absorption layers.

Abstract: A nuclear fuel pellet for a nuclear reactor is disclosed. The pellet comprises a metallic matrix and ceramic fuel particles of a fissile material dispersed in the metallic matrix. The metallic matrix is an alloy consisting of the principle elements U, Zr, Nb and Ti, and of possible rest elements. The concentration of each of the principle elements in the metallic matrix is at the most 50 molar-%.

Abstract: A fuel assembly for a nuclear reactor, a fuel rod of the fuel assembly, and a ceramic nuclear fuel pellet of the fuel rod are disclosed. The fuel pellet includes a first fissile material of UB2, The boron of the UB2 is enriched to have a concentration of the isotope 11B that is higher than for natural B.

Abstract: A fuel assembly for a nuclear reactor, a fuel rod of the fuel assembly, and a ceramic nuclear fuel pellet of the fuel rod are disclosed. The fuel pellet includes a first fissile material of UB2, The boron of the UB2 is enriched to have a concentration of the isotope 11B that is higher than for natural B.

Abstract: A tubular ceramic component is provided for being used in a nuclear reactor. The component comprises an inner layer of silicon carbide, an intermediate layer of silicon carbide fibres in a fill material of silicon carbide, and an outer layer of silicon carbide. The intermediate layer adjoins the inner layer. The outer layer adjoins the intermediate layer. The silicon carbide of the inner layer, the fill material and the outer layer is doped and comprises at least one dopant in solid solution within crystals of the silicon carbide.

Abstract: Disclosed are a sintered nuclear fuel pellet, a fuel rod, a fuel assembly and a method of manufacturing the nuclear fuel pellet. The pellet comprises a matrix of UO2 and particles dispersed in the matrix. The particles comprises a uranium-containing material. Each of the particles is encapsulated by a metallic coating. The uranium-containing material has a uranium density that is higher than the uranium density of UO2. The metallic coating consists of at least one metal chosen from the group of Mo, W, Cr, V and Nb.

Abstract: A nuclear fuel pellet for a nuclear reactor is disclosed. The pellet comprises a metallic matrix and ceramic fuel particles of a fissile material dispersed in the metallic matrix. The metallic matrix is an alloy consisting of the principle elements U, Zr, Nb and Ti, and of possible rest elements. The concentration of each of the principle elements in the metallic matrix is at the most 50 molar-%.

Abstract: The method described herein may be characterized as reacting uranium dioxide with carbon to produce uranium carbide, and, reacting the uranium carbide with a silane, a silicon halide, a siloxane, or combinations thereof, and excess hydrogen to produce uranium silicide.

Abstract: The method described herein may be characterized as reacting uranium dioxide with carbon to produce uranium carbide, and, reacting the uranium carbide with a silane, a silicon halide, a siloxane, or combinations thereof, and excess hydrogen to produce uranium silicide.

Abstract: A method is described herein for coating the substrate of a component for use in a water cooled nuclear reactor to provide a barrier against corrosion. The method includes providing a zirconium alloy substrate; and coating the substrate with particles selected from the group consisting of metal oxides, metal nitrides, FeCrAl, FeCrAlY, and high entropy alloys. Depending on the metal alloy chosen for the coating material, a cold spray or a plasma arc spray process may be employed for depositing various particles onto the substrate. An interlayer of a different material, such as a Mo, Nb, Ta, or W transition metal or a high entropy alloy, may be positioned in between the Zr-alloy substrate and corrosion barrier layer.