200336 ⎘
Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel; Reprocessing of irradiated fuel of irradiated solid fuel Non-aqueous processes
FISSION PRODUCT TRAP FOR SALT PIPE AND PUMP SHAFT SEALS AND METHODS OF USE THEREOF
#2MODULAR, INTEGRATED, AUTOMATED, COMPACT, AND PROLIFERATION-HARDENED METHOD TO CHEMICALLY RECYCLE USED NUCLEAR FUEL (UNF) ORIGINATING FROM NUCLEAR REACTORS TO RECOVER A MIXTURE OF TRANSURANIC (TRU) ELEMENTS FOR ADVANCED REACTOR FUEL, AND TO RECYCLE URANIUM AND ZIRCONIUM
#3ELECTROCHEMICAL CELLS FOR DIRECT OXIDE REDUCTION, AND RELATED METHODS
#4Light water reactor uranium fuel assembly and operation method of nuclear fuel cycle
#5Injectable sacrificial material systems and methods to contain molten corium in nuclear accidents
#6Method and facility for converting uranium hexafluoride into uranium dioxide
#7Equipment for producing nuclear fuel powder
#8ELECTROCHEMICAL CELLS FOR DIRECT OXIDE REDUCTION, AND RELATED METHODS
#9Continuous reprocessing of spent nuclear fuel
#10Conversion of spent uranium oxide fuel into molten salt reactor fuel
#11Electrochemical cells for direct oxide reduction, and related methods
#12Spent fuel dry-process reprocessing method for directly obtaining zirconium alloy nuclear fuel
#13Integral U/TRU recovery cathode system for electrorefining used nuclear fuel, method for electrorefining and harvesting metal from used nuclear fuel
#14Nuclear fuel structure and method of making a nuclear fuel structure using a detachable cathode material
#15Method and system for generating electricity using waste nuclear fuel
#16Method of recovering nuclear fuel material
#17Methods of fabricating metallic fuel from surplus plutonium
#18Process for separating at least one first chemical element Efrom at least one second chemical element E, involving the use of a medium comprising a specific molten salt
#19Modular cathode assemblies and methods of using the same for electrochemical reduction
#20Process for preparing an oxyhalogenide and/or oxide of actinide(s) and/or of lanthanide(s) from a medium comprising at least one molten salt
#21PROCESS AND DEVICE FOR BRINGING TWO IMMISCIBLE LIQUIDS INTO CONTACT, WITHOUT MIXING AND AT HIGH TEMPERATURE, WITH HEATING AND KNEADING BY INDUCTION
#22Method of recycling spent nuclear fuel
#23Advanced dry head-end reprocessing of light water reactor spent nuclear fuel
#24Method for corium and used nuclear fuel stabilization processing
#25NUCLEAR REACTORS AND RELATED METHODS AND APPARATUS
#26METHOD FOR EXTRACTING AT LEAST ONE CHEMICAL ELEMENT FROM A MOLTEN SALT MEDIUM
#27Modular anode assemblies and methods of using the same for electrochemical reduction
#28Modular cathode assemblies and methods of using the same for electrochemical reduction
#29Method and device for contacting two immiscible liquids without mixing them
#30Advanced dry head-end reprocessing of light water reactor spent nuclear fuel
#31Encapsulation of nano-materials for fluid purification/separation
#32Compositions and methods for treating nuclear fuel
#33Method for recovery of residual actinide elements from chloride molten salt
#34METHOD FOR PROCESSING NUCLEAR FUELS CONTAINING SILICON CARBIDE AND FOR DECLADDING NUCLEAR FUEL PARTICLES
#35Process for Converting Alkaline-Earth Metal Chlorides to Tungstates and Molybdates and Applications Thereof
#36Two step dry UOproduction process utilizing a positive sealing valve means between steps
#37Method for extraction of metals by methyliminobisalkylacetamide
#38Processing materials
#39Pyrochemical reprocessing method for spent nuclear fuel
#40Vol-oxidizer for spent nuclear fuel
#41Non-aqueous method for separating chemical constituents in spent nuclear reactor fuel
#42Device for irradiating a target with a hadron-charged beam, use in hadrontherapy
#43Injectable sacrificial material systems and methods to contain molten corium in nuclear accidents
#44Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel