A method for producing microencapsulated fuel pebble fuel more rapidly and with a matrix that engenders added safety attributes. The method includes coating fuel particles with ceramic powder; placing the coated fuel particles in a first die; applying a first current and a first pressure to the first die so as to form a fuel pebble by direct current sintering. The method may further include removing the fuel pebble from the first die and placing the fuel pebble within a bed of non-fueled matrix ceramic in a second die; and applying a second current and a second pressure to the second die so as to form a composite fuel pebble.

Ceramic-bonded diamond composite particle includes a plurality of diamond grains and silicon carbide reaction bonded to the diamond grains having a composition of 60-90 wt. % diamond, 10-40 wt. % silicon carbide, ≦2 wt. % silicon. Particles are formed by processes that forms granules in a pre-consolidation process, forms a densified compact including ceramic-bonded diamond composite material in a consolidation process or forms ceramic-bonded diamond composite material directly, and a post-consolidation process in which the densified compact or ceramic-bonded diamond composite material is mechanically broken to form a plurality of the particles. Inert or active material can be incorporated into the densified compact or coated on granules to reduce the number and extent of diamond to silicon carbide bonding occurring in the consolidation process and make the ceramic-bonded diamond composite material more friable and easily breakable into composite particles.

The present invention relates to a method for preparing a fully ceramic capsulated nuclear fuel material containing three-layer-structured isotropic nuclear fuel particles coated with a ceramic having a composition which has a higher shrinkage than a matrix in order to prevent cracking of ceramic nuclear fuel, wherein the three-layer-structured nuclear fuel particles before coating is included in the range of between 5 and 40 fractions by volume based on after sintering. More specifically, the present invention provides a composition for preparing a fully ceramic capsulated nuclear fuel containing three-layer-structured isotropic particles coated with the substance which includes, as a main ingredient, a silicon carbine derived from a precursor of the silicon carbide wherein a condition of ΔL.sub.c>ΔL.sub.m at normal pressure sintering is created, where the sintering shrinkage of the coating layer of the three-layer-structured isotropic nuclear fuel particles is ΔL.sub.c and the sintering shrinkage of the silicon carbide matrix is ΔL.sub.m; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.

A method of manufacturing ceramic matrix composites includes producing chemical vapor deposition functionalized ceramic particles before injecting the functionalized ceramic particles into the CMC fabric. The functionalized ceramic particles are mixed with a binder solution and then dispensed into voids present between adjacent tows of the CMC fabric. Injecting the particles in the center of the voids reduces the size and volume fraction of the voids/defects, improving the homogeneity of surface texture, homogeneity of microstructure, and part model shape conformity.

A complex composite particle is made of a coal dust and binder composite that is pyrolyzed. Constituent portions of the composite react together causing the particles to increase in density and reduce in size during pyrolyzation, yielding a particle suitable for use as a proppant or in a composite structure.

The present invention relates to a method for producing an electrode material for a battery electrode, in particular for a lithium-ion battery, wherein said electrode material comprises nanostructured silicon carbide, comprising the steps of: a) providing a mixture including a silicon source, a carbon source and a dopant, wherein at least the silicon source and the carbon source are present in common in particles of a solid granulate; b) treating the mixture provided in step a) at a temperature in the range from ≧1400° C. to ≦2000° C., in particular in a range from ≧1650° C. to ≦1850° C., wherein step b) is carried out in a reactor that has a depositing surface the temperature of which relative to at least one other inner reactor surface is reduced. In summary, a method described above enables to combine a simple and cost-efficient production with a high cycle stability.

A method for producing microencapsulated fuel pebble fuel more rapidly and with a matrix that engenders added safety attributes. The method includes coating fuel particles with ceramic powder; placing the coated fuel particles in a first die; applying a first current and a first pressure to the first die so as to form a fuel pebble by direct current sintering. The method may further include removing the fuel pebble from the first die and placing the fuel pebble within a bed of non-fueled matrix ceramic in a second die; and applying a second current and a second pressure to the second die so as to form a composite fuel pebble.

A method for producing microencapsulated fuel pebble fuel more rapidly and with a matrix that engenders added safety attributes. The method includes coating fuel particles with ceramic powder; placing the coated fuel particles in a first die; applying a first current and a first pressure to the first die so as to form a fuel pebble by direct current sintering. The method may further include removing the fuel pebble from the first die and placing the fuel pebble within a bed of non-fueled matrix ceramic in a second die; and applying a second current and a second pressure to the second die so as to form a composite fuel pebble.

The present invention relates to a method for preparing a fully ceramic capsulated nuclear fuel material containing three-layer-structured isotropic nuclear fuel particles coated with a ceramic having a composition which has a higher shrinkage than a matrix in order to prevent cracking of ceramic nuclear fuel, wherein the three-layer-structured nuclear fuel particles before coating is included in the range of between 5 and 40 fractions by volume based on after sintering. More specifically, the present invention provides a composition for preparing a fully ceramic capsulated nuclear fuel containing three-layer-structured isotropic particles coated with the substance which includes, as a main ingredient, a silicon carbine derived from a precursor of the silicon carbide wherein a condition of ΔL.sub.c>ΔL.sub.m at normal pressure sintering is created, where the sintering shrinkage of the coating layer of the three-layer-structured isotropic nuclear fuel particles is ΔL.sub.c and the sintering shrinkage of the silicon carbide matrix is ΔL.sub.m; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.

The present invention relates to a method for producing an electrode material for a battery electrode, in particular for a lithium-ion battery, wherein said electrode material comprises nanostructured silicon carbide, comprising the steps of: a) providing a mixture including a silicon source, a carbon source and a dopant, wherein at least the silicon source and the carbon source are present in common in particles of a solid granulate; b) treating the mixture provided in step a) at a temperature in the range from ≥1400° C. to ≤2000° C., in particular in a range from ≥1650° C. to ≤1850° C., wherein step b) is carried out in a reactor that has a depositing surface the temperature of which relative to at least one other inner reactor surface is reduced. In summary, a method described above enables to combine a simple and cost-efficient production with a high cycle stability.