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Carbide-based fuel assembly for thermal propulsion applications

Patent ·
OSTI ID:2222015
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.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States); BWXT Advanced Technologies LLC, Lynchburg, VA (United States); BWXT Nuclear Energy, Inc., Charlotte, NC (United States)
Sponsoring Organization:
USDOE; National Aeronautics and Space Administration (NASA)
DOE Contract Number:
AC07-05ID14517
Assignee:
BWXT Advanced Technologies LLC (Lynchburg, VA); BWXT Nuclear Energy, Inc. (Charlotte, NC)
Patent Number(s):
11,710,578
Application Number:
17/399,881
OSTI ID:
2222015
Country of Publication:
United States
Language:
English

References (5)

book
Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor journal October 2015
Nonproliferation improvements and challenges presented by small modular reactors journal April 2015
Nuclear Thermal Propulsion (NTP): A proven growth technology for human NEO/Mars exploration missions conference March 2012
Liquid Metal Fast Breeder Reactor Design Study Final Report report January 1964

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