摘要:
A single integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce U3O8. A fluorination vessel is coupled to the decladding vessel to remove hexafluorides from the U3O8 produced by the decladding vessel. An electrowinning vessel is coupled to the fluorination vessel removing plutonium and actinides via electrowinning.
摘要:
A process for dissolving nuclear fuel, in particular irradiated nuclear fuel, comprising immersion of the nuclear fuel in a nitric acid solution. This dissolution process further comprises mechanical milling of the nuclear fuel, this mechanical milling being performed in the nitric acid solution during the immersion. The disclosure also relates to the use of a mill equipped with mechanical milling structure to implement the dissolution process.
摘要:
The invention relates to a technique for handling liquid radioactive waste from a nuclear fuel-energy cycle, and may be used in a process for processing liquid radioactive waste for maximally reducing the volume thereof and removing radionuclides by concentrating same in a solid phase. The aim is achieved by means of a method for processing liquid radioactive waste and for the recovery thereof, including waste oxidation, separating sludge, colloids and suspended particles from a liquid phase, and removing, from the liquid phase, radionuclides to be subsequently recovered using selective sorbents and filters; the method is characterized in that, prior to the stage for separating sludge, colloids and suspended particles from the liquid phase of the radioactive waste, selective sorbents in the form of powders are added and mixed into the liquid waste.
摘要:
Apparatus and methods for treating radioactive material, in particular for cleaning radioactive contaminated water, are described. One apparatus comprises a process chamber with a combustion zone for generating an oxygen rich gas and an oxidation zone, which is arranged to receive the oxygen rich gas from the combustion zone. The process chamber further comprises a feed opening for feeding the radioactive material into the oxidation zone and is configured to use the oxygen rich gas for oxidizing the radioactive material to obtain oxidized material. The apparatus further comprises a separation device operationally connected to an outlet of the process chamber and configured to at least partly separate the oxidized material into a gaseous fluid and a non-gaseous residue. This way a greatly reduced volume of the radioactive material is achieved, enabling safe and efficient handling and/or compact and space-saving disposal of the radioactive material.
摘要:
A solid composition comprises: MnO2; and a compound represented by the general formula (I) wherein: R is a polymer; each Y is independently a hydrogen or a negative charge; Z is either hydrogen or is not present; each n is independently 1, 2, 3, 4, 5 or 6; wherein the MnO2 is bound to the compound of formula (I) so as to coat the surface thereof. Such a composition may be used for the separation of polyvalent metal species, such as Mo, from one or more accompanying impurities.
摘要:
The invention relates to a method for preparing a powder of a solid solution of dioxide of uranium and of at least one other actinide and/or lanthanide element comprising a step for combustion of a solution comprising uranyl nitrate and at least one nitrate of the other actinide and/or lanthanide element and nitrogen-containing fuel used according to a specific predetermined amount so as to form at the end of this step, said solid solution.
摘要:
The present invention provides a polymeric extractant with pendant chelator groups for selective sequestration of actinides and/or lanthanides comprising: a first block polymer comprising one or more CMPO monomers each having a first backbone bound to a pendant carbomylmethylphosphine oxide group; a second block polymer comprising one or more second monomers each having a second backbone bound to a second pendant group, wherein the first backbone is polymerized to the second backbone to form a polymer backbone with pendent blocks of the second pendant group and pendent blocks of pendent carbomylmethylphosphine oxide group that sequester the actinides and/or lanthanides; and optionally a third block polymer comprising one or more third monomers each having a third backbone bound to a third pendant group, wherein the one or more third monomers is polymerized to the first backbone and the second backbone.
摘要:
The present invention provides a redox mediated polymer composition for the selective sequestration and separation of multivalent metal ions comprising: 2 or more monomers polymerized to form a polymeric thiophene backbone, wherein each of the 2 or more monomers comprise 2 thiophene portion groups for polymerization and 2 pendant carbomylmethyl-phosphine oxide or diglycolamide groups that sequester selectively the multrivalent metal ions.
摘要:
A process which allows separation of americium present in an acid aqueous phase or in an organic phase from the other metal elements also found in this phase, by complexation of the americium with a water-soluble ethylenediamine derivative; and a process for selective recovery of americium from an acid aqueous phase containing, in addition to americium, other metal elements, which comprises the application of this separation process.
摘要:
The invention relates to the use of a compound of the formula KmgF3 to trap metals in the form of fluorides and/or of oxyfluorides in a gaseous or liquid phase. It also relates to a compound of the formula KMgF3 which has a surface area at least equal to 30 m2/g and at most equal to 150 m2/g and also to its methods of preparation. The invention notably finds application in the nuclear industry, in which it can advantageously be used to purify uranium hexafluoride (UF6) present in a gaseous or liquid stream, with regard to metal impurities which are also present in this stream.