Carbide-based fuel assembly for thermal propulsion applications

FUEL BUNDLE WITH TWISTED RIBBON FUEL RODLETS FOR NUCLEAR THERMAL PROPULSION APPLICATIONS, STRUCTURES FOR MANUFACTURE, AND METHODS OF MANUFACTURE

ADJUSTING WAIT TIME BETWEEN BURN CYCLES OR MERGING BURN CYCLES

Electrochemical uranium nitride production

HIGH DENSITY U02 AND HIGH THERMAL CONDUCTIVITY UO2 COMPOSITES BY SPARK PLASMA SINTERING (SPS)

Carbide-based fuel assembly for thermal propulsion applications

SPARK PLASMA SINTERING METHODS FOR FABRICATING DENSE GRAPHITE

Grain boundary enhanced UN and USipellets with improved oxidation resistance

Method for process for producing fully ceramic microencapsulated fuels containing tristructural-isotropic particles with a coating layer having higher shrinkage than matrix

Fully ceramic microencapsulated fuels containing tristructural-isotropic particles with a coating layer having higher shrinkage than matrix

ADDITION INTO THE FUEL MIXTURE OF NUCLEAR FUEL FOR NUCLEAR REACTORS

Nuclear-fuel sintered pellets based on oxide in which fine precipitate material is dispersed in circumferential direction and method of manufacturing same

Ceramic nuclear fuel having UB2 enriched in 11B

High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS)

Honeycomb-shaped fuel assembly cooled by liquid chloride salt and reactor core using this assembly

Variable propellant density for passive reactivity control of nuclear thermal propulsion reactors

Methods of additively manufacturing a structure

Additive manufacturing technique for placing nuclear reactor fuel within fibers

Nuclear fuel pebble and method of manufacturing the same

Nuclear fuel pellet, a fuel rod, and a fuel assembly

COMPOSITE FUEL WITH ENHANCED OXIDATION RESISTANCE

Nuclear fuel pebble and method of manufacturing the same

Grain boundary enhanced UN and U3Si2 pellets with improved oxidation resistance

Aqueous additive production method for the fabrication of metallic bodies

MOX fuel assembly

Fully ceramic capsulated nuclear fuel composition containing three-layer-structured isotropic nuclear fuel particles with coating layer having higher shrinkage than matrix, material thereof and method for preparing the same

Methods of forming structures and fissile fuel materials by additive manufacturing

Nuclear fuel pebble and method of manufacturing the same

Nuclear fuel particle having a pressure vessel comprising layers of pyrolytic graphite and silicon carbide

Fully ceramic microencapsulated fuel fabricated with burnable poison as sintering aid

Modular nuclear fission waste conversion reactor

Additive manufacturing technique for placing nuclear reactor fuel within fibers

Dispersion ceramic micro-encapsulated (DCM) nuclear fuel and related methods

Method for fabrication of fully ceramic microencapsulation nuclear fuel

A FUEL ASSEMBLY FOR A NUCLEAR REACTOR

Nuclear fuel pebble and method of manufacturing the same

Nuclear fuel pebble and method of manufacturing the same

FULLY CERAMIC NUCLEAR FUEL AND RELATED METHODS

High density UOand high thermal conductivity UOcomposites by spark plasma sintering (SPS)

Target device for neutron generating device, accelerator-excited neutron generating device and beam coupling method thereof

Method and device for generating droplets over a variable spectrum of particle sizes

Nuclear fuel

METHOD FOR PREPARING A POROUS NUCLEAR FUEL

Uranium dioxide nuclear fuel pellet having ceramic microcells

Nuclear fuel containing a neutron absorber

Nuclear fuel containing recycled and depleted uranium, and nuclear fuel bundle and nuclear reactor comprising same

FULLY CERAMIC MICROENCAPSULATED REPLACEMENT FUEL ASSEMBLIES FOR LIGHT WATER REACTORS

Fully ceramic nuclear fuel and related methods

Method of controlling solubility of additives at and near grain boundaries, and method of manufacturing sintered nuclear fuel pellet having large grain size using the same

Connection device for a system for filling jars for the production of nuclear fuel

NUCLEAR FUEL ASSEMBLY AND RELATED METHODS FOR SPENT NUCLEAR FUEL REPROCESSING AND MANAGEMENT

Method and arrangement for producing fuel kernels

Method for preparing an actinide(s) oxalate and for preparing an actinide(s) compound

NUCLEAR FUEL, A FUEL ELEMENT, A FUEL ASSEMBLY AND A METHOD OF MANUFACTURING A NUCLEAR FUEL

Method for preparing a mixed fuel comprising uranium and at least one actinide and/or lanthanide applying a cation exchange resin

MANUFACTURING METHOD OF NUCLEAR FUEL PELLET, FUEL ASSEMBLY FOR NUCLEAR REACTOR AND MANUFACTURING METHOD THEREOF AND URANIUM POWDER

Method of manufacturing nuclear fuel elements and a container for implementing such a method

USE OF ISOTOPICALLY ENRICHED NITROGEN IN ACTINIDE FUEL IN NUCLEAR REACTORS

Method for the production of spherical combustible or fertile material particles

Process for manufacturing enhanced thermal conductivity oxide nuclear fuel and the nuclear fuel

Process for the manufacture of a particulate material and particulate material obtained by this process

Plutonium/Zirconium Hydride/Thorium Fuel Matrix

Fuel Pellet for a Nuclear Reactor and Method for Producing Fuel Pellet

Nuclear fuel

Method of manufacturing sinter-active UOpowder and method of producing nuclear fuel pellets utilizing the same

MOX fuel assembly for pressurized nuclear reactors

Non Proliferating Thorium Nuclear Fuel Inert Metal Matrix Alloys for Fast Spectrum and Thermal Spectrum Thorium Converter Reactors

Process for manufacturing enhanced thermal conductivity oxide nuclear fuel and the nuclear fuel

Apparatus For Manufacturing Coated Fuel Particles For High-Temperature Gas-Cooled Reactor

Reactor tray vertical geometry with vitrified waste control

Method for the Production of Nuclear Fuel Pellets

Nuclear Fuel

Method for producing ceramic nuclear fuel tablets, device and container for carrying out said method

Use of boron or enriched boron 10 in UO

Mox fuel assembly for pressurized water reactors

Use of isotopically enriched actinide fuel in nuclear reactors

Reactor tray vertical geometry with vitrified waste control

Use of boron or enriched boron 10 in UO

Method for coprecipitation of actinides in different oxidation states and method for preparation of mixed compounds of actinides

Use of isotopically enriched nitride in actinide fuel in nuclear reactors

Fuel pellet for a nuclear reactor and method for producing the fuel pellet

Reactor tray vertical geometry with vitrified waste control

Fabrication of uranium nitride