ALD coating of nuclear fuel actinides materials
The invention provides a method of forming a nuclear fuel pellet of a uranium containing fuel alternative to UO 2 , with the steps of obtaining a fuel form in a powdered state; coating the fuel form in a powdered state with at least one layer of a material; and sintering the powdered fuel form into a fuel pellet. Also provided is a sintered nuclear fuel pellet of a uranium containing fuel alternative to UO 2 , wherein the pellet is made from particles of fuel, wherein the particles of fuel are particles of a uranium containing moiety, and wherein the fuel particles are coated with at least one layer between about 1 nm to about 4 nm thick of a material using atomic layer deposition, and wherein the at least one layer of the material substantially surrounds each interfacial grain barrier after the powdered fuel form has been sintered.
1. A sintered nuclear fuel pellet, wherein said pellet includes particles of fuel, wherein each of the particles comprises a uranium containing moiety,
wherein the uranium containing moiety is selected from the group consisting of uranium nitrides, uranium carbides, uranium-zirconium hydrides, uranium-molybdenum alloys, and combinations thereof,
wherein said pellet includes an atomic layer deposition (ALD) provided coating on the particles,
wherein the coating comprises at least one layer of material,
wherein the at least one layer is about 1 nm to about 4 nm thick,
wherein the at least one layer of material is a metal-containing compound selected from the group consisting of alumina, zirconium oxide, silicon carbide, silicon dioxide, magnesium oxide, zirconium nitride, zirconium hydride, silicon nitride, aluminum nitride, zirconium, molybdenum, silicon, gadolinium oxide, titanium nitride, calcium oxide, and combinations thereof, and
wherein the at least one layer of the material substantially surrounds each particle before and after the particles have been sintered.
2. The fuel pellet of claim 1 wherein the volume percent of the at least one layer of material is no more than 30% of the volume of the fuel pellet when the uranium containing moiety is uranium nitride.
3. The fuel pellet of claim 1 wherein the volume percent of the at least one layer of material is no more than 20% of the volume of the fuel pellet when the uranium containing moiety is uranium carbide.
4. The fuel pellet of claim 1 wherein each of the particles is coated with a plurality of layers of material.
5. The fuel pellet of claim 1 wherein each of the particles is coated with a plurality of layers of material wherein the volume percent of the plurality of layers of material is no more than 20% of the volume of the fuel pellet.
6. The fuel pellet of claim 1 wherein the sintered fuel pellet has a uranium density of approximately 90%.
7. The fuel pellet of claim 1 , wherein the coating is uniform.
8. The fuel particle of claim 4 where each of the plurality of layers of material comprises a different material.
9. The fuel particle of claim 5 wherein each of the plurality of layers of material comprises a different material.
10. The fuel particle of claim 1 wherein each of the particle is coated with a plurality of layers of material wherein the volume percent of the plurality of layers of material is no more than 30% of the volume of the fuel pellet.