Abstract:
A method with which americium may be selectively recovered from a nitric aqueous phase containing americium, curium and fission products including lanthanides and yttrium, but which is free of uranium, plutonium and neptunium or which only contains these three last elements in trace amounts. The method is applicable for treatment and recycling of irradiated nuclear fuels, in particular for removing americium from raffinates stemming from methods for extracting and purifying uranium and plutonium such as the PUREX and COEX™ methods.
Abstract:
A method with which americium may be selectively recovered from a nitric aqueous phase containing americium, curium and fission products including lanthanides and yttrium, but which is free of uranium, plutonium and neptunium or which only contains these three last elements in trace amounts. The method is applicable for treatment and recycling of irradiated nuclear fuels, in particular for removing americium from raffinates stemming from methods for extracting and purifying uranium and plutonium such as the PUREX and COEX™ methods.
Abstract:
The invention relates to a process which makes it possible to separate together all the actinide(III), (IV), (V) and (VI) entities present in a highly acidic aqueous phase from fission products, in particular lanthanides, also present in this phase by using a solvating extractant in a salting-out medium.Applications: reprocessing of irradiated nuclear fuels, in particular for recovering plutonium, neptunium, americium, curium and possibly uranium, present in the form of traces, in a pooled but selective fashion with regard to lanthanides, from a solution for the dissolution of an irradiated nuclear fuel, downstream of a cycle for the extraction of uranium.
Abstract:
The invention relates to a method for separating uranium(VI) from one or more actinides selected from actinides(IV) and actinides(VI) other than uranium(VI), characterized in that it comprises the following steps:a) bringing an organic phase, which is immiscible with water and contains the said uranium and the said actinide or actinides, in contact with an aqueous acidic solution containing at least one lacunary heteropolyanion and, if the said actinide or at least one of the said actinides is an actinide(VI), a reducing agent capable of selectively reducing this actinide(VI); andb) separating the said organic phase from the said aqueous solution.Applications: reprocessing irradiated nuclear fuels, processing rare-earth, thorium and/or uranium ores.
Abstract:
Alpine ski binding (1) comprising a base plate (2), to which a boot position-retention element (3) and a ski brake (8) are assembled. The base plate (2) is designed to be integrally attached to the ski using screws (14, 15). The ski brake incorporates a seating (10) superposed to the base plate (2), and the base is assembled to the base plate through the cooperation of tenons (18, 19) and mortises (20, 21) in the base plate (2). The brake (8) is, moreover, assembled to the base plate (2) by a movable locking device (23). The front screws used to assemble the binding to the ski pass through both the seating (10) of the brake (8) and the front part of the base plate (2), and their heads rest on the base plate (10) of the brake. The binding is delivered with the brake assembled, and, subsequently, dismantling the brake is possible by loosening the front screws (14) and by opening the locking device (23).
Abstract:
A method using diglycolamide for increasing the separation factor between americium and curium and/or between lanthanides during an extraction operation. The operation comprising putting an acid aqueous phase, in which are found the americium, curium and/or lanthanides, in contact with an organic phase non-miscible with water, containing at least one extractant in an organic diluent. The aqueous and organic phases are then separated, and the diglycolamide is added to the aqueous phase. This method can be used for processing and recycling irradiated nuclear fuels, in particular for selectively recovering americium from high activity aqueous solutions such as raffinates stemming from the processing of irradiated nuclear fuels with a PUREX or COEX™ method; processing of rare earth ores of the monazite, xenotime or bastnaesite type, in order to facilitate separation of > rare earths from > rare earths and of yttrium, or that of two rare earths with adjacent or close atomic numbers.
Abstract:
The invention relates to a process for reprocessing spent nuclear fuel which, among other advantages, does not require a plutonium-reducing stripping operation.This process finds particular application in the processing of uranium oxide fuels and uranium and plutonium mixed oxide fuels.