Dispersion ceramic micro-encapsulated (DCM) nuclear fuel and related methods
View Patent ↗The invention relates to the use of Dispersion Ceramic Micro-Encapsulated (DCM) nuclear fuel as a meltdown-proof, accident-tolerant fuel to replace uranium dioxide fuel in existing light water reactors (LWRs). The safety qualities of the DCM fuel are obtained by the combination of three strong barriers to fission product release (ceramic coatings around the fuel kernels), highly dense inert ceramic matrix around the coated fuel particles and metallic or ceramic cladding around the fuel pellets.
1. A nuclear fuel comprising:
a dispersion-ceramic micro-encapsulated fuel comprising a plurality of tristructural-isotropic (TRISO) fuel particles embedded in a silicon carbide matrix;
wherein the plurality of TRISO fuel particles each include one or more layers of isotropic materials surrounding a fuel kernel and the fuel kernel is surrounded by a porous carbon buffer layer, an inner pyrolytic carbon layer, a ceramic layer, and an outer pyrolytic carbon layer;
wherein the ceramic layer is formed of a silicon carbide layer supplemented with a zirconium carbide; and
wherein the plurality of TRISO fuel particles includes two or more different sizes of TRISO fuel particles, including a first TRISO fuel particle having a first fuel kernel with a first kernel radius of no more than 375 micrometers and a first packing fraction of no more than 45% and a second TRISO fuel particle having a second fuel kernel with a second kernel radius of no more than 200 micrometers and a second packing fraction of no more than 3%.
2. The nuclear fuel of claim 1 , wherein the dispersion-ceramic micro-encapsulated fuel is comprised of heavy metal materials providing higher density than uranium dioxide.
3. The nuclear fuel of claim 2 , wherein the heavy metal materials are selected from a group consisting of uranium nitride, uranium carbide, and uranium silicide.
4. The nuclear fuel of claim 3 , wherein the fuel includes resonant absorbers selected from a group consisting of gadolinium or erbium.
5. The nuclear fuel of claim 1 , wherein the silicon carbide matrix comprises silicon carbide powder mixed with sintering additives.
6. The nuclear fuel of claim 1 , wherein the fuel kernel includes a fissile material and a fertile material in an oxide, carbide, or oxycarbide form.
7. The nuclear fuel of claim 6 , wherein the fertile material is selected from a group consisting of uranium, plutonium, or thorium.
8. The nuclear fuel of claim 1 , wherein the fuel kernel comprises low enriched uranium.
9. The nuclear fuel of claim 1 , wherein the porous carbon buffer layer surrounds the fuel kernel and is a reservoir for accommodating buildup of fission gases diffusing out of the fuel kernel and mechanical deformation that the fuel kernel undergoes during a fuel cycle.
10. The nuclear fuel of claim 1 , wherein the ceramic layer is formed of silicon carbide material.
11. The nuclear fuel of claim 1 , wherein the first TRISO fuel particle has a pellet radius between 0.4095 and 0.4709 centimeters and a pellet height of 1 centimeter.
12. The nuclear fuel of claim 11 , wherein:
the porous carbon buffer layer of the first TRISO fuel particle has a porous carbon buffer layer radius of 0.0475 centimeters;
the inner pyrolytic carbon layer of the first TRISO fuel particle has an inner pyrolytic carbon radius of 0.0510 centimeters;
the ceramic layer of the first TRISO fuel particle has a ceramic layer radius of 0.0545 centimeters; and
the outer pyrolytic carbon layer of the first TRISO fuel particle has an outer pyrolytic carbon layer radius of 0.0585 centimeters.
13. The nuclear fuel of claim 12 , wherein the second TRISO fuel particle has a pellet radius of 0.4709 centimeters and a pellet height of 1 centimeter.
14. The nuclear fuel of claim 13 , wherein:
the porous carbon buffer layer radius of the second TRISO fuel particle is 0.0300 centimeters;
the inner pyrolytic carbon layer radius of the second TRISO fuel particle is 0.0335 centimeters;
the ceramic layer radius of the second TRISO fuel particle is 0.0370 centimeters; and
the outer pyrolytic carbon layer radius is 0.0410 centimeters.
15. The nuclear fuel of claim 14 , wherein the fuel kernel comprises uranium nitride.
16. The nuclear fuel of claim 14 , wherein the fuel kernel comprises uranium carbide.