Patent Number: 
Section: claims

1. Microstructured nuclear fuel adapted for use in a nuclear power system, comprising fissile material structures comprising spherical fuel particles of up to 5 micrometers in diameter for each fuel particle of said fuel particles, and the fuel particles are dispersed in an inert matrix, said inert matrix enabling most of the fission product atoms to escape from the particle and become lodged in the matrix during use of the fuel in said nuclear power system and thereby enabling most of the fission products to be readily separated from the fissile material. 2. The microstructured nuclear fuel of claim 1, wherein the inert matrix is carbon. 3. The microstructured nuclear fuel of claim 1, wherein the inert matrix material is selected from the group consisting of MgO, Al2O3, Y2O3, ZrO2, CeO2, NbO2, and TaO2. 4. The microstructured nuclear fuel of claim 1, wherein the inert matrix material is selected from the group consisting of Mg3N2, AlN, Si3N4, YN, ZrN, and CeN. 5. The microstructured nuclear fuel of claim 1, wherein the inert matrix material is selected from the group consisting of SiC and ZrC. 6. The microstructured nuclear fuel of claim 1, wherein the inert matrix material is selected from the group consisting of MgAl2O4, ZrSiO4, YPO4, and CePO4. 7. The microstructured nuclear fuel of claim 1, wherein the inert matrix material is 1-5 micrometers thick. 8. Microstructured nuclear fuel adapted for use in a nuclear power system, comprising fissile material structures comprising fuel cylinders of up to 5 micrometers in diameter for each fuel particle of said fuel particles, and the fuel particles are dispersed in an inert matrix, said inert matrix enabling most of the fission product atoms to escape from the particle and become lodged in the matrix during use of the fuel in said nuclear power system and thereby enabling most of the fission products to be readily separated from the fissile material. 9. The microstructured nuclear fuel of claim 8, wherein the inert matrix is carbon. 10. The microstructured nuclear fuel of claim 8, wherein the inert matrix material is selected from the group consisting of MgO, Al2O3, Y2O3, ZrO2, CeO2, NbO2, and TaO2. 11. The microstructured nuclear fuel of claim 8, wherein the inert matrix material is selected from the group consisting of Mg3N2, AlN, Si3N4, YN, ZrN, and CeN. 12. The microstructured nuclear fuel of claim 8, wherein the inert matrix material is selected from the group consisting of SiC, and ZrC. 13. The microstructured nuclear fuel of claim 8, wherein the inert matrix material is selected from the group consisting of MgAl2O4, ZrSiO4, YPO4, and CePO4. 14. The microstructured nuclear fuel of claim 8, wherein the inert matrix material is 1-5 micrometers thick.