ORDERED PARTICLE FUEL

Experimental system and method for high-temperature oxidation and quenching of cladding materials under reactor severe accident

ZIRCONIUM-GRAPHENE COVETIC MATERIAL FOR NUCLEAR FUEL CELL CLADDING APPLICATIONS

NUCLEAR FUEL CLADDING AND METHOD FOR PRODUCING SUCH CLADDING

CLADDING AND ASSEMBLY FOR NUCLEAR APPLICATIONS

A NUCLEAR FUEL ROD CLADDING TUBE AND A METHOD FOR MANUFACTURING A NUCLEAR FUEL ROD CLADDING TUBE

NUCLEAR FUEL ELEMENT

SINGLE WALLED CARBON NANOTUBE-BASED SLURRY FOR IMPROVED NUCLEAR FUEL CLADDING COATINGS AND METHOD OF FABRICATION OF SAME

PLATE-SHAPED NUCLEAR FUEL ELEMENT AND METHOD OF MANUFACTURING THE SAME

NUCLEAR FUEL RODS AND HEAT PIPES IN A GRAPHITE MODERATOR MATRIX FOR A MICRO-REACTOR, WITH THE FUEL RODS HAVING FUEL PELLETS IN A BeO SLEEVE

ENCAPSULATED PEBBLE

METHOD FOR MANUFACTURING MULTI-LAYERED NUCLEAR FUEL CLADDING AND MULTI-LAYERED NUCLEAR FUEL CLADDING PRODUCED THEREBY

EFFECTIVE COATING MORPHOLOGY TO PROTECT ZR ALLOY CLADDING FROM OXIDATION AND HYDRIDING

METHOD FOR DEPOSITION OF DENSE CHROMIUM ON A SUBSTRATE

USE OF OXIDATION RESISTANT COATINGS TO INCREASE THIN WALLED CLADDING TENSILE STRENGTH TO INCREASE URANIUM LOADINGS

CERAMIC COATING FOR CORROSION RESISTANCE OF NUCLEAR FUEL CLADDING

NUCLEAR FUEL ROD AND MANUFACTURING METHOD

FUEL CLADDING COVERED BY A MESH

Multi-Layered Nuclear Fuel Cladding and Method for Manufacturing Multi-Layered Nuclear Fuel Cladding

COATINGS AND SURFACE MODIFICATIONS TO MITIGATE SiC CLADDING DURING OPERATION IN LIGHT WATER REACTORS

Processing ultra high temperature zirconium carbide microencapsulated nuclear fuel

CARBIDE-BASED FUEL ASSEMBLY FOR THERMAL PROPULSION APPLICATIONS

COMPOSITE NUCLEAR COMPONENT, DLI-MOCVD METHOD FOR PRODUCING SAME, AND USES FOR CONTROLLING OXIDATION/HYDRIDATION

NUCLEAR FUEL CLADDING ELEMENT AND METHOD OF MANUFACTURING SAID CLADDING ELEMENT

Process of Manufacture a Nuclear Component with Metal Substrate by Dlimocvd and Method against Oxidation/Hydriding of Nuclear Component

NUCLEAR FUEL CLADDING FOR FAST REACTORS, ASSEMBLIES THEREOF, AND METHODS OF MANUFACTURE THEREOF

PLATED METALLIC SUBSTRATES AND METHODS OF MANUFACTURE THEREOF

A cladding tube for a fuel rod for a nuclear reactor, a fuel rod, and a fuel assembly

HYDROGEN-RESISTANT COATINGS AND ASSOCIATED SYSTEMS AND METHODS

ANTI-FOULING COATINGS AND ASSOCIATED SYSTEMS AND METHODS

ANNULAR NUCLEAR FUEL ROD

Silicon carbide reinforced zirconium based cladding

END PLUG FOR SEALING COMPOSITE TUBULAR CERAMIC CLADDING OF FUEL ELEMENT OF NUCLEAR REACTOR (VARIANTS), AND METHOD FOR MANUFACTURING SAME (VARIANTS)

CATHODIC ARC APPLIED RANDOMIZED GRAIN STRUCTURED COATINGS ON ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING

PHYSICAL VAPOR DEPOSITION OF CERAMIC COATINGS ON ZIRCONIUM ALLOY NUCLEAR FUEL RODS

3D printed features on nuclear fuel cladding for optimized heat transfer

Method for producing ceramic multilayered tube used as cladding for fuel element in nuclear power plant

Channel box and fuel assembly

Tubular component of pressurised water nuclear reactor, and method for manufacturing said component

210Pb and 227Ac Precursor Isotopes in Radioisotope Power Systems

Nuclear fuel rods and heat pipes in a graphite moderator matrix for a micro-reactor, with the fuel rods having fuel pellets in a BeO sleeve

Nuclear reactor fuel assembly manufacturing method

MOLTEN METAL-FILLED SILICON CARBIDE FUEL CLADDING TUBE AND UNIFORM DISTRIBUTION FABRICATION METHOD

STEEL-VANADIUM ALLOY CLADDING FOR FUEL ELEMENT

Carbide-based fuel assembly for thermal propulsion applications

Control rods for light water reactors

A cladding tube for a fuel rod for nuclear reactors

SELF-HEALING LIQUID PELLET-CLADDING GAP HEAT TRANSFER FILLER

Structural material for molten salt reactors

Processing ultra high temperature zirconium carbide microencapsulated nuclear fuel

NUCLEAR COMPONENT WITH METASTABLE CR COATING, DLI-MOCVD METHOD FOR PRODUCING SAME, AND USES FOR CONTROLLING OXIDATION/HYDRIDATION

Fuel design and shielding design for radioisotope thermoelectric generators

METHOD TO PRESSURIZE SIC FUEL CLADDING TUBE BEFORE END PLUG SEALING BY PRESSURIZATION PUSHING SPRING LOADED END PLUG

Single walled carbon nanotube-based slurry for improved nuclear fuel cladding coatings and method of fabrication of same

Nuclear fuel pellet laminate structure having enhanced thermal conductivity and method for manufacturing the same

Zirconium-coated silicon carbide fuel cladding for accident tolerant fuel application

Joining and sealing pressurized ceramic structures

Reactor fuel pellets with thermally-conductive inserts, and related reactor fuel pellet arrangements

Nuclear reactor component having a coating of amorphous chromium carbide

Coated fuel pellets with enhanced water and steam oxidation resistance

Processing ultra high temperature zirconium carbide microencapsulated nuclear fuel

Elongate SiC fuel elements

A tubular ceramic component suitable for being used in a nuclear reactor

Steel-vanadium alloy cladding for fuel element

A cladding tube, and a method of manufacturing a cladding tube

Radiation resistant high-entropy alloy having FCC structure and preparation method thereof

Zirconium alloy cladding with improved oxidation resistance at high temperature and method for manufacturing same

Enhanced surface treatments

A sintered nuclear fuel pellet, a fuel rod, a fuel assembly, and a method of manufacturing a sintered nuclear fuel pellet

Nuclear component with metastable Cr coating, DLI-MOCVD method for producing same, and uses for controlling oxidation/hydridation

Additive manufacturing technique for placing nuclear reactor fuel within fibers

Coatings and Surface Modifications to Mitigate SiC Cladding During Operation in Light Water Reactors

High Yield ICF Target for Large Radiation Gains

Tubular body containing SiC fiber and method for producing the same

MULTI-LAYERED NUCLEAR FUEL CLADDING AND METHOD FOR MANUFACTURING MULTI-LAYERED NUCLEAR FUEL CLADDING

Double-sealed fuel rod end plug for ceramic-containing cladding

Method for dynamic pressure control in a fluid injector system

Method of manufacturing a corrosion-resistant zirconium alloy for a nuclear fuel cladding tube

Transition metal-based materials for use in high temperature and corrosive environments

Cold spray chromium coating for nuclear fuel rods

Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer

Process of manufacture a nuclear component with metal substrate by DLI-MOCVD and method against oxidation/hydriding of nuclear component

Manufacture of large grain powders with granular coatings

ANNULAR METAL NUCLEAR FUEL AND METHODS OF MANUFACTURING THE SAME

STEEL-VANADIUM ALLOY CLADDING FOR FUEL ELEMENT

ENGINEERED SIC-SIC COMPOSITE AND MONOLITHIC SIC LAYERED STRUCTURES

Iron-based composition for fuel element

Composite nuclear component, DLI-MOCVD method for producing same, and uses for controlling oxidation/hydridation

Silicon carbide reinforced zirconium based cladding

Method to pressurize sic fuel cladding tube before end plug sealing by pressurization pushing spring loaded end plug

Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application

HIGH TEMPERATURE NUCLEAR FUEL SYSTEM FOR THERMAL NEUTRON REACTORS

Nuclear reactor having a layer protecting the surface of zirconium alloys

Control rods for light water reactors

Welded joint between a fuel element casing and a plug

Method of sealing nuclear reactor fuel elements having a casing made of ferrite-martensite steel

KINETICALLY APPLIED GRADATED Zr-Al-C OR Ti-Al-C CERAMIC OR AMORPHOUS OR SEMI-AMORPHOUS STAINLESS STEEL WITH NUCLEAR GRADE ZIRCONIUM ALLOY METAL STRUCTURE

CLADDING FOR A FUEL ROD FOR A LIGHT WATER REACTOR

Method for joining silicon carbide components to one another

CERAMIC COATING FOR CORROSION RESISTANCE OF NUCLEAR FUEL CLADDING

Thermal-neutron reactor core and design method for thermal-neutron reactor core

METHOD OF MANUFACTURE

Coated U3Si2 pellets with enhanced water and steam oxidation resistance

Method for producing nuclear fuel products by cold spraying a core comprising aluminum and low enriched uranium

Fuel rods with wear-inhibiting coatings

Steel-vanadium alloy cladding for fuel element

Fuel assembly, core design method and fuel assembly design method of light-water reactor

METHOD OF MANUFACTURING ZIRCONIUM NUCLEAR FUEL COMPONENT USING MULTI-PASS HOT ROLLING

Duplex accident tolerant coating for nuclear fuel rods

Corrosion and wear resistant coating on zirconium alloy cladding

SPRAY METHODS FOR COATING NUCLEAR FUEL RODS TO ADD CORROSION RESISTANT BARRIER

Cold spray chromium coating for nuclear fuel rods

Nuclear fuel rod

Method of manufacturing a SiC composite fuel cladding with inner Zr alloy liner

Zirconium-coated silicon carbide fuel cladding for accident tolerant fuel application

Rod assembly for nuclear reactors

Nuclear reactor fuel rod and fuel assembly having bundled same

Light water reactor fuel rod having ceramic cladding tube and ceramic end plug

HIGH TEMPERATURE, RADIATION-RESISTANT, FERRITIC-MARTENSITIC STEELS

Nuclear fuel claddings, production method thereof and uses of same against oxidation/hydriding

Process for rapid processing of SiC and graphitic matrix TRISO-bearing pebble fuels

Modular nuclear fission waste conversion reactor

Additive manufacturing technique for placing nuclear reactor fuel within fibers

METHOD AND FUEL DESIGN TO STABILIZE BOILING WATER REACTORS

Fuel rods with wear-inhibiting coatings and methods of making the same

Iron-based composition for fuel element

Chemical optimisation in a molten salt reactor

Corrosion and wear resistant coating on zirconium alloy cladding

Method for fabrication of fully ceramic microencapsulation nuclear fuel

SiC matrix fuel cladding tube with spark plasma sintered end plugs

Enhanced surface treatments

Entropy-controlled BCC alloy having strong resistance to high-temperature neutron radiation damage

ZIRCONIUM ALLOY HAVING EXCELLENT CORROSION RESISTANCE FOR NUCLEAR FUEL CLADDING TUBE AND METHOD OF MANUFACTURING THE SAME

Method for fabricating silicon carbide assemblies

IRON-BASED COMPOSITION FOR FUEL ELEMENT

Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application

LAYER PROTECTING THE SURFACE OF ZIRCONIUM ALLOYS USED IN NUCLEAR REACTORS

Fuel rod cladding, fuel rod and fuel assembly

Water-soluble coating composition for surface protection of nuclear fuel rod

Traveling wave nuclear fission reactor, fuel assembly, and method of utilizing control rods to control burnfront

Sinter bonded containment tube

METHOD OF PLATINUM INJECTION INTO A NUCLEAR REACTOR

SILICON CARBIDE MULTILAYERED CLADDING AND NUCLEAR REACTOR FUEL ELEMENT FOR USE IN WATER-COOLED NUCLEAR POWER REACTORS

CERAMIC STRUCTURE

Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy

Organically Cooled Nuclear Reactor for Enhanced Economics and Safety

Deposition of a protective coating including metal-containing and chromium-containing layers on zirconium alloy for nuclear power applications

Method for producing nuclear fuel products with a high loading of LEU and corresponding nuclear fuel product

Zirconium alloys with improved corrosion/creep resistance due to final heat treatments

Structure, electronic element module, heat exchanger, fuel rod, and fuel assembly

Zirconium alloys with improved corrosion/creep resistance

Cladding tube for nuclear fuel rod, method and apparatus for manufacturing a cladding

Nuclear fuel rod cladding including a metal nanomaterial layer

Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application

SiC matrix fuel cladding tube with spark plasma sintered end plugs

ALD coating of nuclear fuel actinides materials

Coating of nuclear fuel cladding materials, method for coating nuclear fuel cladding materials

Fuel rod cladding and methods for making and using same

Designed porosity materials in nuclear reactor components

Multilayer material resistant to oxidation in a nuclear environment

Fuel rod assembly and method for mitigating the radiation-enhanced corrosion of a zirconium-based component

Composite fuel rod cladding

Nuclear reactor cores comprising a plurality of fuel elements, and fuel elements for use therein

Methods of fine forming sapphire tubes and joining sapphire components for nuclear reactor fuel elements and assemblies

Fuel rods with wear-inhibiting coatings and methods of making the same

METHOD FOR PRODUCING A WEAR-RESISTANT AND CORROSION-RESISTANT STAINLESS STEEL PART FOR A NUCLEAR REACTOR, CORRESPONDING PART AND CORRESPONDING CONTROL CLUSTER

Nanocrystalline/amorphous composite coating for protecting metal components in nuclear plants cooled with liquid metal or molten salt

Nuclear fuel

NUCLEAR REACTOR FUEL ELEMENT HAVING SILICON CARBIDE MULTILAYERED CLADDING AND THORIA-BASED FISSIONABLE FUEL

Method and apparatus for a fret resistant fuel rod for a light water reactor (LWR) nuclear fuel bundle

Multilayer tube in ceramic matrix composite material, resulting nuclear fuel cladding and associated manufacturing processes

System and method for annealing nuclear fission reactor materials

Deposition of integrated protective material into zirconium cladding for nuclear reactors by high-velocity thermal application

Method for producing a composite including a ceramic matrix

ZIRCONIUM ALLOY WITH COATING LAYER CONTAINING MIXED LAYER FORMED ON SURFACE, AND PREPARATION METHOD THEREOF

Metal nuclear-fuel pin including a shell having threads or fibers made of silicon carbide (SiC)

EXTENSION OF METHODS TO UTILIZE FULLY CERAMIC MICRO-ENCAPSULATED FUEL IN LIGHT WATER REACTORS

Zirconium alloy for improving resistance to oxidation at very high temperature and fabrication method thereof

Sealed containment tube

SURFACE MODIFICATION OF CLADDING MATERIAL

Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a severe reactor operation condition and methods of preparing a zirconium alloy nuclear cladding by using thereof

Zirconium alloys for a nuclear fuel cladding having a superior corrosion resistance by reducing an amount of alloying elements and methods of preparing a zirconium alloy nuclear fuel cladding using thereof

Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a reactor accident condition, zirconium alloy nuclear fuel claddings prepared by using thereof and methods of preparing the same

Nuclear fuel rod for fast reactor

FULLY CERAMIC MICROENCAPSULATED REPLACEMENT FUEL ASSEMBLIES FOR LIGHT WATER REACTORS

CERAMIC ENCAPSULATIONS FOR NUCLEAR MATERIALS AND SYSTEMS AND METHODS OF PRODUCTION AND USE

Nuclear fuel rod and method of manufacturing pellets for such a rod

Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods

Zirconium alloy material

High Cr ferritic/martensitic steels having an improved creep resistance for in-core component materials in nuclear reactor, and preparation method thereof

Cladding material, tube including such cladding material and methods of forming the same

Superwetting surfaces for diminishing leidenfrost effect, methods of making and devices incorporating the same

Zirconium alloys with improved corrosion/creep resistance due to final heat treatments

FUEL CHANNEL ARRANGED TO BE COMPRISED BY A FUEL ELEMENT FOR A FISSION REACTOR

CLADDING TUBE FOR NUCLEAR FUEL ROD, METHOD AND APPARATUS FOR MANUFACTURING A CLADDING TUBE

Nuclear fuel cladding with high heat conductivity and method for making same

Alloy and tube for nuclear fuel assembly and method for making same

Nuclear fuel cladding having an exterior comprising burnable poison in contact with aqueous reactor coolant

Water reactor fuel cladding tube

PROCESS OF MANUFACTURING ZIRCONIUM ALLOY FOR FUEL GUIDE TUBE AND MEASURING TUBE HAVING HIGH STRENGTH AND EXCELLENT CORROSION RESISTANCE

Particulate metal fuels used in power generation, recycling systems, and small modular reactors

Traveling wave nuclear fission reactor, fuel assembly, and method of controlling burnup therein

Traveling wave nuclear fission reactor, fuel assembly, and method of controlling burnup therein

ZIRCONIUM ALLOYS WITH IMPROVED CORROSION RESISTANCE AND METHOD FOR FABRICATING ZIRCONIUM ALLOYS WITH IMPROVED CORROSION RESISTANCE

Zirconium alloy resistant to corrosion in drop shadows for a fuel assembly component for a boiling water reactor, component produced using said alloy, fuel assembly, and use of same

Method of forming a silicon carbide material, and structures including the material

ZIRCONIUM ALLOY COMPOSITION FOR NUCLEAR FUEL CLADDING TUBE FORMING PROTECTIVE OXIDE FILM, ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBE MANUFACTURED USING THE COMPOSITION, AND METHOD OF MANUFACTURING THE ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBE

Fuel rod assembly and method for mitigating the radiation-enhanced corrosion of a zirconium-based component

Method for designing a fuel assembly optimized as a function of the stresses in use in light-water nuclear reactors, and resulting fuel assembly

System and method for annealing nuclear fission reactor materials

System and method for annealing nuclear fission reactor materials

ERBIUM-CONTAINING ZIRCONIUM ALLOY, METHODS FOR PREPARING AND SHAPING THE SAME, AND STRUCTURAL COMPONENT CONTAINING SAID ALLOY.

Tubular body and method for producing the same

Removal of niobium second phase particle deposits from pickled zirconium-niobium alloys

Nuclear fuel

Method for Operating a Nuclear Reactor and Use of a Specific Fuel Rod Cladding Alloy in Order to Reduce Damage Caused by Pellet/Cladding Interaction

METHOD, USE AND DEVICE CONCERNING CLADDING TUBES FOR NUCLEAR FUEL AND A FUEL ASSEMBLY FOR A NUCLEAR PRESSURE WATER REACTOR

Multi-layered ceramic tube for fuel containment barrier and other applications in nuclear and fossil power plants

Method of applying a burnable poison onto the exterior of nuclear rod cladding

Removal of niobium second phase particle deposits from pickled zirconium-niobium alloys

High Fe contained zirconium alloy compositions having excellent corrosion resistance and preparation method thereof

Clad tube for nuclear fuel

ZIRCONIUM ALLOY COMPOSITION HAVING EXCELLENT CORROSION RESISTANCE FOR NUCLEAR APPLICATIONS AND METHOD OF PREPARING THE SAME

Method of manufacturing a fuel cladding tube for a nuclear reactor, and a tube obtained thereby

Method for operating a nuclear reactor and use of a specific fuel rod cladding alloy in order to reduce damage caused by pellet/cladding interaction

Precursor formulation of a silicon carbide material

LWR flow channel with reduced susceptibility to deformation and control blade interference under exposure to neutron radiation and corrosion fields

Zirconium-niobium oxygen-containing alloy and method for producing said alloy

Zirconium alloys with improved corrosion resistance and method for fabricating zirconium alloys with improved corrosion

High heat flux rate nuclear fuel cladding and other nuclear reactor components

Fuel element for a pressurized water reactor

Methods of reducing hydrogen absorption in zirconium alloys of nuclear fuel assemblies

Method, use and device concerning cladding tubes for nuclear fuel and a fuel assembly for a nuclear pressure water reactor

Method of producing a zirconium alloy semi-finished product for the production of elongated product and use thereof

Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same

Multi-layered ceramic tube for fuel containment barrier and other applications in nuclear and fossil power plants

Method, use and device concerning cladding tubes for nuclear fuel and a fuel assembly for a nuclear boiling water reactor

Method of manufacturing reactor member by using the surface treatment method

Zirconium-based alloy having a high resistance to corrosion and to hydriding by water and steam and process for the thermomechanical transformation of the alloy

Zirconium-based alloy and method for making a component for nuclear fuel assembly with same