A method of forming a composite component is provided. The method includes locating a fibrous preform, providing a slurry, mixing the slurry with sacrificial fibers, injecting the slurry into the fibrous preform, heating the fibrous preform, forming channels in the fibrous preform, and densifying the fibrous preform. The sacrificial fibers are suspended in the fibrous preform along an injection pathway such that heating the sacrificial fibers forms the channels along the injection pathway as the sacrificial fibers are burned away.

Disclosed are compositions containing nanoparticles of a metal nitride, boride, silicide, or carbide, a filler material, and a carbonaceous matrix. The precursor to this material contains nanoparticles or particles of boron, silicon, iron, a refractory metal, or a refractory metal hydride, an organic compound having carbon and hydrogen, and a filler material. Multilayered materials are also disclosed.

A metallurgical vessel structure and method is provided for producing low-impurity Magnesia-Carbon reclaimed aggregate suitable for reuse in the production of high purity Magnesia-Carbon refractory. A metallurgical vessel is assembled with a non-reactive or chemically similar backup lining. The entire height of the working lining wall is Magnesia-Carbon brick suitable for reuse. The working lining is exposed to a metal making high temperature process, and the working lining is sequentially demolished. Due to the assembly of vessel, metallurgical practice, and ease of demolishing the vessel, there is little to no need for sorting, such that the used Magnesia-Carbon brick are easily converted into low impurity Magnesia-Carbon reclaimed aggregate. A refractory composed of low-impurity Magnesia aggregate reclaimed from the method is also contemplated.

A nuclear reactor system includes a nuclear reactor core disposed in a pressure vessel. Nuclear reactor system further includes control drums disposed longitudinally within the pressure vessel and laterally surrounding fuel elements and at least one moderator element of the nuclear reactor core to control reactivity. Each of the control drums includes a reflector material and an absorber material. Nuclear reactor system further includes an automatic shutdown controller and an electrical drive mechanism coupled to rotatably control the control drum. Automatic shutdown controller includes a counterweight to impart a bias and an actuator. To automatically shut down the nuclear reactor core during a loss or interruption of electrical power from a power source to the electrical drive mechanism, the actuator is coupled to the counterweight and responsive to the bias to align the absorber material of one or more control drums to face inwards towards the nuclear reactor core.

An antiballistic armor-plating component, includes a ceramic body made of a material including, as percentages by volume, between 20% and 75% of boron carbide, between 5% an d 30% of a metallic silicon phase or of a metallic phase including silicon and between 20% and 70% of silicon carbide and wherein, as percentages by volume: more than 60% of the grains with an equivalent diameter greater than 60 micrometers are boron carbide grains, the boron carbide grains with an equivalent diameter greater than 30 micrometers represent more than 20%, the silicon carbide grains with an equivalent diameter greater than or equal to 10 micrometers represent more than 10%, the silicon carbide grains with an equivalent diameter less than 10 micrometers represent more than 10%.

An enhanced architecture for a nuclear reactor core includes several technologies: (1) nuclear fuel tiles (S-Block); and (2) a high-temperature thermal insulator and tube liners with a low-temperature solid-phase moderator (U-Mod) to improve safety, reliability, heat transfer, efficiency, and compactness. In S-Block, nuclear fuel tiles include a fuel shape designed with an interlocking geometry pattern to optimize heat transfer between nuclear fuel tiles and into a fuel coolant and bring the fuel coolant in direct contact with the nuclear fuel tiles. Nuclear fuel tiles can be shaped with discontinuous nuclear fuel lateral facets and have fuel coolant passages formed therein to provide direct contact between the fuel coolant and the nuclear fuel tiles. In U-Mod, tube liners with low hydrogen diffusivity retain hydrogen in the low-temperature solid-phase moderator even at elevated temperatures and the high-temperature thermal insulator insulates the solid-phase moderator from the nuclear fuel tiles.

An electrophoretic deposition method of forming a boron nitride (BN) nanotube interface coating on ceramic fibers has been developed. The method comprises immersing first and second electrodes in a suspension including surface-modified BN nanotubes, where the first electrode includes ceramic fibers positioned on a surface thereof. The surface-modified BN nanotubes comprise BN nanotubes with an electrically charged polymer adsorbed on surfaces thereof. A voltage is applied to the first and second electrodes, and the surface-modified BN nanotubes move toward the first electrode and deposit on the ceramic fibers. After the deposition of the surface-modified BN nanotubes, the ceramic fibers are removed from the suspension and heat treated. Accordingly, a BN nanotube interface coating is formed on the ceramic fibers.

The present invention relates to a coating composition comprising: 10 to 80 wt % of cerium oxide comprising a dopant based upon the total weight of the composition, wherein said dopant is selected from iron oxide, cobalt oxide, chromium oxide, lanthanum oxide, or mixtures thereof, and the atomic ratio of dopant metal to cerium is in the range 0.01:1 to 0.5:1; and 10 to 50 wt % of binder based upon the total weight of the composition.

The invention relates to a sliding member having a first sliding surface, wherein the first sliding surface (29) comprises a particulate support material (6) and a graphene-containing material (7), wherein the particulate support material (6) is at least partially coated with the graphene-containing material (7), and wherein a material bond (14) is present between the particulate support material (6) and the graphene-containing material (7).

Improved formulations of an interface material are described. These formulations may, in at least some cases, match and/or accommodate dimensional changes in the part and/or support structure throughout thermal processing (e.g., debind and sintering, or sintering only). Furthermore, these formulations may also maintain the property of resisting bonding between the interface and the part and/or support structure while also maintaining a physical separation between the part and support structure. In some cases, an improved interface material may accommodate strain associated with the shrinkage of a part (and optionally support structure) during sintering while also minimally impacting the ability of the part (and optionally support structure) to shrink or otherwise change in dimension. In some cases, the interface material may include one or more fugitive phases that are removed during thermal processing (e.g., through pyrolysis of the fugitive phase(s)).