Annular nuclear fuel pellets with central burnable absorber
An annular nuclear fuel pellet in combination with an inserted discrete neutron absorber. The pellet/absorber may be compatible with existing or future nuclear fuel assembly designs. The concept involves the use of nuclear fuel (e.g., uranium dioxide or uranium silicide) formed into annular fuel pellets which can then have a discrete absorber material inserted into the center of the pin. Preferably, the discrete absorber is a non-parasitic absorber. The resulting pellet/absorber can then be stacked into a fuel rod which is arranged in a nuclear fuel assembly. Dimensioning of the annular pellet and absorber and selection of the absorber material and density can allow the concept to be tailored for various nuclear fuel applications.
1. A nuclear fuel assembly comprising:
a parallel array of elongated nuclear fuel rods supported in a spaced relationship with each other, between a lower nozzle and an upper nozzle and having an axial length along the elongated dimension of the nuclear fuel rods;
at least some of the nuclear fuel rods comprise:
a tubular cladding extending over the axial length and closed at a lower end by a bottom end plug and closed at an upper end by a top end plug;
a stack of a plurality of fuel pellets occupying a lower portion of an interior of the cladding with at least some of the fuel pellets in the stack of fuel pellets having an annular shape with a central opening;
a discrete neutron absorber substantially occupying the central opening of at least some of the annular fuel pellets, and the discrete neutron absorber is free of fissile material and primarily comprised of boron or boron carbide, wherein the discrete neutron absorber is structured as a rod; and
a metallic coating applied to at least one of an inside surface of the central opening of the annular fuel pellets and an outside surface of the discrete neutron absorber, opposite the inside surface, wherein the metallic coating is selected from the group consisting of molybdenum, a molybdenum alloy, tungsten, and a tungsten alloy, wherein the metallic coating has a total thickness in a range of 0.5 to 100 um.
2. The nuclear fuel assembly of claim 1 wherein the discrete neutron absorber consists of a neutron absorbing material.
3. The nuclear fuel assembly of claim 2 wherein the discrete neutron absorber consists of boron, boron carbide, or a boron carbide and aluminum oxide mixture.
4. The nuclear fuel assembly of claim 1 wherein the discrete neutron absorber is structured as a rod and is sized to extend through the central opening in more than one annular fuel pellet.
5. The nuclear fuel assembly of claim 1 wherein one or more of the annular fuel pellets with a discrete neutron absorber in the central opening is inserted between two fuel pellets without a central discrete absorber.
6. The nuclear fuel assembly of claim 5 wherein the two fuel pellets without a central discrete absorber are solid fuel pellets without a central opening.
7. The nuclear fuel assembly of claim 1 wherein the coating is applied with a physical vapor deposition, an atomic layer deposition, a cold spray or an electroplating process.
8. A nuclear reactor having a core comprising a plurality of nuclear fuel assemblies, with at least some of the fuel assemblies comprising:
a parallel array of elongated nuclear fuel rods supported in a spaced relationship with each other, between a lower nozzle and an upper nozzle and having an axial length along the elongated dimension of the nuclear fuel rods;
at least some of the nuclear fuel rods comprise:
a tubular cladding extending over the axial length and closed at a lower end by a bottom end plug and closed at an upper end by a top end plug;
a stack of a plurality of fuel pellets occupying a lower portion of an interior of the cladding with at least some of the fuel pellets in the stack of fuel pellets having an annular shape with a central opening;
a discrete neutron absorber substantially occupying the central opening of at least some of the annular fuel pellets,
and the discrete neutron absorber is free of fissile material; and
a metallic coating applied to at least one of an inside surface of the central opening of the annular fuel pellets and an outside surface of the discrete neutron absorber, opposite the inside surface, wherein the metallic coating is selected from the group consisting of molybdenum, a molybdenum alloy, tungsten, and a tungsten alloy, wherein the metallic coating has a total thickness in a range of 0.5 to 100 um.
9. A nuclear fuel assembly comprising:
a stack of a plurality of fuel pellets, wherein at least some of the fuel pellets in the stack of fuel pellets have an annular shape defining an annulus;
a pin disposed within the annulus of the at least some of the fuel pellets, the pin consists of boron, boron carbide, silver-indium-cadmium, or a boron carbide and aluminum oxide mixture; and
a metallic coating applied to at least one of an inside surface of the fuel pellets and an outside surface of the pin, opposite the inside surface, wherein the metallic coating is selected from the group consisting of molybdenum, a molybdenum alloy, tungsten, and a tungsten alloy, wherein the metallic coating has a total thickness in a range of 0.5 to 100 um.
10. The nuclear fuel assembly of claim 9 , wherein the plurality of fuel pellets comprise uranium dioxide, uranium nitride, uranium silicide, or a combination thereof.
11. The nuclear fuel assembly of claim 9 , wherein the pin extends through the annulus of at least five fuel pellets of the plurality of fuel pellets.
12. The nuclear fuel assembly of claim 9 , wherein the metallic coating is applied to at least the inside surface of the fuel pellets.
13. The nuclear fuel assembly of claim 9 , wherein the metallic coating is applied to at least the outside surface of the pin.
14. The nuclear fuel assembly of claim 9 , wherein the metallic coating consists of tungsten.
15. The nuclear fuel assembly of claim 9 , wherein the annular shape is a continuous annular shape.
16. The nuclear fuel assembly of claim 9 wherein the pin is sized to extend through the a central opening in only one annular fuel pellet.
17. The nuclear fuel assembly of claim 9 wherein the coating is applied with a physical vapor deposition, an atomic layer deposition, a cold spray, or an electroplating process.
18. The nuclear fuel assembly of claim 9 wherein the metallic coating has a total thickness of less than 1 um.