Using additive manufacturing in creating a nuclear fuel structure with a shape corresponding to a mathematically-based periodic solid having a triply periodic minimal surface

US12437891B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-12437891-B2
Application numberUS-202318386031-A
CountryUS
Kind codeB2
Filing dateNov 1, 2023
Priority dateApr 1, 2019
Publication dateOct 7, 2025
Grant dateOct 7, 2025

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  5. First independent claim

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Abstract

Official abstract text for this publication.

A method of manufacturing a nuclear fuel segment includes varying a parameter of a lattice structure of a first mathematically-based periodic solid to form a second mathematically-based periodic solid. The second mathematically-based periodic solid comprises a triply periodic minimal surface (TPMS). The varying includes varying periodicity, thickness, or bias of the first mathematically-based periodic solid. The second mathematically-based periodic solid is embodied in a gridded mesh. The gridded mesh is sectioned into a plurality of layers. An additive manufacturing process is used to deposit a fissionable fuel composition in creating a body having a structure with a shape corresponding to the second mathematically-based periodic solid. The plurality of layers are used in controlling the additive manufacturing process.

First claim

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What is claimed is: 1. A method of manufacturing a nuclear fuel segment, the method comprising: varying a parameter of a lattice structure of a first mathematically-based periodic solid to form a second mathematically-based periodic solid, wherein the second mathematically-based periodic solid comprises a triply periodic minimal surface (TPMS) and wherein varying the parameter includes: varying a periodicity of the first mathematically-based periodic solid, varying a thickness of the first mathematically-based periodic solid, or varying a bias of the first mathematically-based periodic solid, where the bias relates to converging and diverging regions within the second mathematically-based periodic solid; embodying the second mathematically-based periodic solid in a gridded mesh; sectioning the gridded mesh into a plurality of layers; and using the plurality of layers to control an additive manufacturing process to deposit a fissionable fuel composition to manufacture a body having a structure with a shape corresponding to the second mathematically-based periodic solid. 2. The method of claim 1 , wherein the body having the structure with the shape corresponding to the second mathematically-based periodic solid includes a network of interconnected channels, and wherein varying the parameter changes a flow rate of a medium flowing through the network of interconnected channels. 3. The method of claim 2 , wherein at least a portion of the interconnected channels of the network of interconnected channels extend from a first outer surface of the body to a second outer surface of the body, wherein the structure has a volumetric density of 35% to 85%, and wherein a composition of the structure includes a nuclear fissionable fuel having an enrichment of up to 20%. 4. The method according to claim 3 , wherein a specific enrichment of the structure (% enrichment per unit volume) is constant ±2%. 5. The method according to claim 2 , further comprising depositing a cladding layer on surfaces of the network of interconnected channels. 6. The method according to claim 5 , wherein depositing the cladding layer includes a vapor deposition technique, a chemical vapor deposition technique, electroplating or electroless plating. 7. The method according to claim 5 , wherein the cladding has a composition including molybdenum, tungsten, rhenium, tantalum, hafnium and alloys thereof, including carbides. 8. The method according to claim 5 , wherein the cladding layer has a composition including a steel alloy, a zirconium alloy, a molybdenum-containing metal alloy, a molybdenum-tungsten alloy, Zircaloy-4 or Hastelloy X. 9. The method of claim 1 , wherein varying the parameter changes a neutronic characteristic of a nuclear reactor incorporating a fuel element containing the nuclear fuel segment. 10. The method according to claim 9 , wherein the body having the structure with the shape corresponding to the second mathematically-based periodic solid includes a network of interconnected channels, and wherein the method further comprises depositing a cladding layer on surfaces of the network of interconnected channels. 11. The method according to claim 10 , wherein depositing the cladding layer includes a vapor deposition technique, a chemical vapor deposition technique, electroplating or electroless plating. 12. The method according to claim 10 , wherein the cladding has a composition including molybdenum, tungsten, rhenium, tantalum, hafnium and alloys thereof, including carbides. 13. The method according to claim 10 , wherein the cladding layer has a composition including a steel alloy, a zirconium alloy, a molybdenum-containing metal alloy, a molybdenum-tungsten alloy, Zircaloy-4 or Hastelloy X. 14. The method of claim 1 , wherein varying the parameter changes a thermal hydraulics characteristic or a stress mechanics characteristic of a nuclear reactor incorporating a fuel element containing the nuclear fuel segment. 15. The method according to claim 14 , wherein the body having the structure with the shape corresponding to the second mathematically-based periodic solid includes a network of interconnected channels, and wherein the method further comprises depositing a cladding layer on surfaces of the network of interconnected channels. 16. The method according to claim 15 , wherein depositing the cladding layer includes a vapor deposition technique, a chemical vapor deposition technique, electroplating or electroless plating. 17. The method according to claim 15 , wherein the cladding has a composition including molybdenum, tungsten, rhenium, tantalum, hafnium and alloys thereof, including carbides. 18. The method according to claim 15 , wherein the cladding layer has a composition including a steel alloy, a zirconium alloy, a molybdenum-containing metal alloy, a molybdenum-tungsten alloy, Zircaloy-4 or Hastelloy X. 19. The method according to claim 1 , wherein at least a portion of the interconnected channels of the network of interconnected channels extend from a first outer surface of the body to a second outer surface of the body, wherein the structure has a volumetric density of 35% to 85%, and wherein a composition of the structure includes a nuclear fissionable fuel having an enrichment of up to 20%. 20. The method according to claim 19 , wherein a specific enrichment of the structure (% enrichment per unit volume) is constant ±2%. 21. The method according to claim 19 , further comprising depositing a cladding layer on surfaces of the network of interconnected channels, wherein depositing the cladding layer includes a vapor deposition technique, a chemical vapor deposition technique, electroplating or electroless plating. 22. The method according to claim 21 , wherein the cladding has a composition including molybdenum, tungsten, rhenium, tantalum, hafnium and alloys thereof, including carbides. 23. The method according to claim 21 , wherein the cladding layer has a composition including a steel alloy, a zirconium alloy, a molybdenum-containing metal alloy, a molybdenum-tungsten alloy, Zircaloy-4 or Hastelloy X. 24. The method according to claim 1 , wherein the additive manufacturing process includes photopolymerization. 25. The method according to claim 1 , wherein the body is disc-shaped and occupies a volume that includes a radial side surface corresponding to a thickness of the body between a first outer surface and a second outer surface, and wherein the method further comprises placing a side wall radially outward of the radial side surface of the body, wherein the side wall has a composition including a neutron thermalizing material, and wherein the neutron thermalizing material has a composition including a zirconium (Zr) alloy, a beryllium (Be) alloy, or graphite. 26. A method of manufacturing a nuclear fuel segment, the method comprising: varying a parameter of a lattice structure of a first mathematically-based periodic solid to form a second mathematically-based periodic solid, wherein the second mathematically-based periodic solid comprises a triply periodic minimal surface (TPMS) and wherein the varying includes varying: a periodicity of the first mathematically-based periodic solid, a thickness of the first mathematically-based periodic solid, and a bias of the first mathematically-based periodic solid, where the bias relates to converging and diverging regions; e

Assignees

Inventors

Classifications

  • Mobile reactors · CPC title

  • Fuel · CPC title

  • Selection of substances for use as neutron-absorbing material · CPC title

  • Ceramic dispersion fuel, e.g. cermet · CPC title

  • Metallic fuel; Intermetallic dispersions · CPC title

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What does patent US12437891B2 cover?
A method of manufacturing a nuclear fuel segment includes varying a parameter of a lattice structure of a first mathematically-based periodic solid to form a second mathematically-based periodic solid. The second mathematically-based periodic solid comprises a triply periodic minimal surface (TPMS). The varying includes varying periodicity, thickness, or bias of the first mathematically-based p…
Who is the assignee on this patent?
Bwxt Advanced Tech Llc
What technology area does this patent fall under?
Primary CPC classification G21C21/02. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Oct 07 2025 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 4 related publications on this page (citations in our corpus or others sharing the same primary CPC).