Sheath for nuclear fuel coated with consumable neutron poison and method of obtaining it.
FR2695507A1
Sheath for nuclear fuel coated with a fission product trap and method for obtaining it.
FR2692880A1
Process for the selective electro-fluorination of alloys or metallic mixtures based on uranium.
FR2687140A1
PROCESS FOR RECOVERING AND PURIFYING VERY ENRICHED URANIUM METALLIC ALLOY.
FR2705660A1
Process for the recovery and purification of a metal alloy based on enriched uranium
FR2683373A1
Nuclear fuel elements comprising an oxide-based fission products trap.
FR2683374A1
Agent for trapping radioactivity of fission products generated in a nuclear fuel element.
FR2670945A1
Process for producing sintered nuclear fuel pellets from solutions and comprising precipitation using hydrogen peroxide in an acid medium.
FR2655467A1
Process for obtaining combustible uo2 pellets from metal without production of effluent.
FR2634048A1
PROCESS FOR THE MANUFACTURE OF NUCLEAR FUEL PELLETS COMPRISING THE PRODUCTION AND USE OF SINKING AND SINTERABLE POWDERS OBTAINED DIRECTLY BY PRECIPITATION OF PEROXIDES
FR2633606A1
Process for separation by precipitation of zirconium contained in uraniferous carbonate solutions
FR2619952A1
Process for cleaning traces of radioactive elements generated during storage of uranium from the processing of irradiated nuclear fuels
ZA8704132B
A method of manufacturing uranium oxide base nuclear fuel pellets
FR2599355A2
Process for the separation, by precipitation, of molybdenum contained in uranium-bearing acidic solutions
FR2584092A1
PROCESS FOR SEPARATING RARE EARTHS AND URANIUM FROM A CONCENTRATE OF UF4 AND THEIR RECOVERY
FR2583404A1
Process for the separation, by precipitation, of molybdene contained in uranyl nitrate solutions.
FR2583403A1
Process for the separation, by precipitation, of molybdene contained in sulfuric or nitric solutions of uranium.
FR2581924A1
PROCESS FOR THE HIGH TEMPERATURE TREATMENT OF AQUEOUS SUSPENSION CONTAINING STABLE DISPERSE-SHAPED CLAYS
ES8702270A1
Device for unloading pellets, particularly nuclear fuel pellets, and storing these pellets in tubes
JO1355B1
High - temperature pretreatment by means of an alkaline aqueous solution of natural metarials having an argillaceous gangue containing al least one usable combuntible element
