Patent Number: 
Section: claims

1. A method of manufacturing a nuclear fuel element configured for use in a high-temperature gas cooled reactor core, the method comprising:forming a base portion of the nuclear fuel element by depositing a powdered matrix material on a substrate, the powder matrix material comprising a mixture of a graphite material and a fibrous material;depositing particles on the base portion in a predetermined pattern to form a first particle layer, by controlling the position of each particle in the first particle layer;depositing the powdered matrix material on the first particle layer to form a first matrix layer;depositing particles on the first matrix layer in a predetermined pattern to form a second particle layer, by controlling the position of each particle in the second particle layer;depositing the powdered matrix material on the second particle layer to form a second matrix layer; andforming a cap portion of the nuclear fuel element by depositing the matrix material comprising a mixture of a graphite material and a fibrous material on a particle layer,wherein the particles comprise nuclear fuel particles. 2. The method of claim 1, wherein:the fibrous material comprises carbon nanotubes, silicon carbide fibers, or a combination thereof; andthe graphite material comprises graphite powder, graphite spheres, or a combination thereof. 3. The method of claim 1, wherein the fibrous material comprises carbon nanotubes and silicon carbide fibers. 4. The method of claim 3, wherein the powdered matrix material comprises, based on the total weight of the matrix material:from about 1 wt % to about 64 wt % of the carbon nanotubes; andfrom about 1 wt % to about 16 wt % of the silicon carbide fibers. 5. The method of claim 1, wherein the powdered matrix material comprises, based on the total weight of the matrix material:from about 20 wt % to about 99 wt % of the graphite material; andfrom about 1 wt % to about 80 wt % of the fibrous material. 6. The method of claim 1, further comprising mixing the graphite material and the fibrous material before depositing the powdered matrix material. 7. The method of claim 1, wherein controlling the position of each particle within the first and second particle layers comprises:loading particles in controlled positions on a deposition head;disposing the deposition head over the base portion or the first matrix layer;releasing the particles from the deposition head; andpressing the particles into the base portion or the first matrix layer,wherein the deposition head is a vacuum deposition head or an electrostatic deposition head. 8. The method of claim 1, wherein:depositing the powdered matrix material on the first particle layer to form a first matrix layer comprises printing a binder on a portion of the deposited matrix material to define the size and shape of the first matrix layer; anddepositing the powdered matrix material on the second particle layer to form a second matrix layer comprises printing a binder on a portion of the deposited matrix material to define the size and shape of the second matrix layer. 9. The method of claim 8, further comprising:pressing the first particle layer before forming the first matrix layer;pressing the first matrix layer before forming the second particle layer;pressing the second particle layer before forming the second matrix layer; andpressing the second matrix layer before forming the cap portion. 10. The method of claim 1, wherein forming a base portion and forming a cap portion each comprise:A) depositing the powdered matrix material comprising a mixture of graphite material and fibrous material;B) pressing the deposited matrix material;C) printing a binder on the pressed matrix material; andrepeating operations A, B, and C; until the corresponding base portion or cap portion has a thickness ranging from 3 mm to 12 mm. 11. The method of claim 1, wherein operation C comprises printing the binder in a pattern having the same shape as a cross-section of the nuclear fuel element. 12. The method of claim 1, wherein the particles deposited in the first matrix layer and the second matrix layer comprise tri-structural-isotropic (TRISO) fuel particles that do not have an overcoat. 13. The method of claim 1, wherein controlling the position of each particle within the first and second particle layers comprises positioning the particles in a fuel zone of the nuclear fuel element that is surrounded by a fuel-free shell of the nuclear fuel element formed of the matrix material. 14. The method of claim 1, wherein the nuclear fuel element is a spherical fuel pebble suitable for use in a pebble bed high temperature gas cooled reactor.