Bwxt Advanced Technologies LLC

Bwxt Nuclear Energy, Inc.

Jonathan K Witter

Benjamin D Fisher

Craig D Gramlich

John R Salasin

James Brian Inman

Roger Dale Ridgeway

Joshua J Bergman

Eric A Barringer

Ryan Trigg Swanson

Jeremy Leslie Gustafson

Matt Ales

Russell R Jensen

Danny Galicki

Matt Krecicki

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.

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

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC—SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a nuclear thermal propulsion reactor.

Carbide-based fuel assembly for thermal propulsion applications

Nuclear propulsion fission reactor structure has an active core region including fuel element structures, a reflector with rotatable neutron absorber structures (such as drum absorbers), and a core former conformal mating the outer surface of the fuel element structures to the reflector. Fuel element structures are arranged abutting nearest neighbor fuel element structures in a tri-pitch design. Cladding bodies defining coolant channels are inserted into and joined to lower and upper core plates to from a continuous structure that is a first portion of the containment structure. The body of the fuel element has a structure with a shape corresponding to a mathematically-based periodic solid, such as a triply periodic minimal surface (TPMS) in a gyroid structure. The nuclear propulsion fission reactor structure can be incorporated into a nuclear thermal propulsion engine for propulsion applications, such as space propulsion.

Functionally graded lattice cermet fuel structure with shape corresponding to a mathematically-based periodic solid, particularly for nuclear thermal propulsion applications

Functionally graded lattice cermet fuel structure with shape corresponding to a mathematically-based periodic solid, particularly for nuclear thermal propulsion

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. Continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. A fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC&#x2014;SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a nuclear thermal propulsion reactor.

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Forest, VA, United States of America

Jonathan K Witter