Abstract: 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. A 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. 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.

Abstract: 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).

Abstract: 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.

Abstract: 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).

Abstract: Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.

Abstract: Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.

Abstract: Plurality of layers form a nuclear fission reactor structure, each layer having an inner segment body, an intermediate segment body, and an outer segment body (each segment body separated by an interface). The layers include a plurality of cladding arms having involute curve shapes that spirally radiate outward from a radially inner end to a radially outer end. Chambers in the involute curve shaped cladding arm contain fuel compositions (and/or other materials such as moderators and poisons). The design of the involute curve shaped cladding arms and the composition of the materials conform to neutronic and thermal management requirements for the nuclear fission reactor and are of sufficiently common design and/or have sufficiently few variations as to reduce manufacturing complexity and manufacturing variability.

Abstract: 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. A 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 has 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 NTP reactor.

Abstract: 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).

Abstract: Plurality of layers form a nuclear fission reactor structure, each layer having an inner segment body, an intermediate segment body, and an outer segment body (each segment body separated by an interface). The layers include a plurality of cladding arms having involute curve shapes that spirally radiate outward from a radially inner end to a radially outer end. Chambers in the involute curve shaped cladding arm contain fuel compositions (and/or other materials such as moderators and poisons). The design of the involute curve shaped cladding arms and the composition of the materials conform to neutronic and thermal management requirements for the nuclear fission reactor and are of sufficiently common design and/or have sufficiently few variations as to reduce manufacturing complexity and manufacturing variability.

Abstract: Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.

Abstract: Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.

Abstract: A method for brachytherapy in a lumpectomy cavity of a breast including, positioning a distal end of a brachytherapy device within the cavity, expanding an expandable surface portion located between proximal and distal ends of the device within the cavity, the source lumen tubes defining a curved configuration within the cavity; and positioning a source of radiation sequentially within one or more source lumens of the source lumen tubes according to a brachytherapy treatment plan. The device includes an inner tube, and a plurality of source lumen tubes located around the inner tube and including distal ends secured together with the inner tube at the distal end disposed within the body cavity, the source lumen tubes comprising proximal portions sufficiently long to extend outside the breast.

Abstract: A method for brachytherapy in a lumpectomy cavity of a breast including, positioning a distal end of a brachytherapy device within the cavity, expanding an expandable surface portion located between proximal and distal ends of the device within the cavity, the source lumen tubes defining a curved configuration within the cavity; and positioning a source of radiation sequentially within one or more source lumens of the source lumen tubes according to a brachytherapy treatment plan. The device includes an inner tube, and a plurality of source lumen tubes located around the inner tube and including distal ends secured together with the inner tube at the distal end disposed within the body cavity, the source lumen tubes comprising proximal portions sufficiently long to extend outside the breast.

Abstract: A method for brachytherapy in a lumpectomy cavity of a breast including, positioning a distal end of a brachytherapy device within the cavity, expanding an expandable surface portion located between proximal and distal ends of the device within the cavity, the source lumen tubes defining a curved configuration within the cavity; and positioning a source of radiation sequentially within one or more source lumens of the source lumen tubes according to a brachytherapy treatment plan. The device includes an inner tube, and a plurality of source lumen tubes located around the inner tube and including distal ends secured together with the inner tube at the distal end disposed within the body cavity, the source lumen tubes comprising proximal portions sufficiently long to extend outside the breast.

Abstract: A brachytherapy device for the provision of brachytherapy is disclosed. The brachytherapy device has at least one source lumen located outside a movable surface of the device. The source lumen may be secured to the movable outer surface in a manner whereby relative movement of the source lumen relative to the movable outer surface is permitted. The brachytherapy device is inserted into a body cavity. After insertion, the movable surface is moved to position the at least one source lumen closer to the tissue boundary of the cavity. One or more sources of radiation are then placed within the at least one source lumen to provide a customizable treatment. Also disclosed are methods for providing brachytherapy via body cavities.

Abstract: A method for brachytherapy in a lumpectomy cavity of a breast including, positioning a distal end of a brachytherapy device within the cavity, expanding an expandable surface portion located between proximal and distal ends of the device within the cavity, the source lumen tubes defining a curved configuration within the cavity; and positioning a source of radiation sequentially within one or more source lumens of the source lumen tubes according to a brachytherapy treatment plan. The device includes an inner tube, and a plurality of source lumen tubes located around the inner tube and including distal ends secured together with the inner tube at the distal end disposed within the body cavity, the source lumen tubes comprising proximal portions sufficiently long to extend outside the breast.

Abstract: A method for brachytherapy in a lumpectomy cavity of a breast including, positioning a distal end of a brachytherapy device within the cavity, expanding an expandable surface portion located between proximal and distal ends of the device within the cavity, the source lumen tubes defining a curved configuration within the cavity; and positioning a source of radiation sequentially within one or more source lumens of the source lumen tubes according to a brachytherapy treatment plan. The device includes an inner tube, and a plurality of source lumen tubes located around the inner tube and including distal ends secured together with the inner tube at the distal end disposed within the body cavity, the source lumen tubes comprising proximal portions sufficiently long to extend outside the breast.

Abstract: A method for brachytherapy in a lumpectomy cavity of a breast including, positioning a distal end of a brachytherapy device within the cavity, expanding an expandable surface portion located between proximal and distal ends of the device within the cavity, the source lumen tubes defining a curved configuration within the cavity; and positioning a source of radiation sequentially within one or more source lumens of the source lumen tubes according to a brachytherapy treatment plan. The device includes an inner tube, and a plurality of source lumen tubes located around the inner tube and including distal ends secured together with the inner tube at the distal end disposed within the body cavity, the source lumen tubes comprising proximal portions sufficiently long to extend outside the breast.

Abstract: A method for brachytherapy in a lumpectomy cavity of a breast including, positioning a distal end of a brachytherapy device within the cavity, expanding an expandable surface portion located between proximal and distal ends of the device within the cavity, the source lumen tubes defining a curved configuration within the cavity; and positioning a source of radiation sequentially within one or more source lumens of the source lumen tubes according to a brachytherapy treatment plan. The device includes an inner tube, and a plurality of source lumen tubes located around the inner tube and including distal ends secured together with the inner tube at the distal end disposed within the body cavity, the source lumen tubes comprising proximal portions sufficiently long to extend outside the breast.