11 results about "Minor actinide" patented technology

The application belongs to the technical field of separation and extraction, and particularly relates to a 8C-DAPhen ligand, a preparation method and application thereof. The method is developed from the design of a ligand molecular structure, and a novel cyclic DAPhen ligand is developed through specific structure design. The ligand has a separation factor (SF Eu / Am ) of more than 600 for lanthanide and actinide elements, and exhibits excellent separation performance. The application provides a new perspective for in-depth understanding of lanthanide and actinide separation mechanism, and provides technical support for establishing an advanced spent nuclear fuel reprocessing system and realizing efficient utilization of minor actinide elements.

The invention belongs to the technical field of nuclear reactor cores, and particularly relates to a modular multipurpose lead-bismuth fast reactor core and a design method. The method comprises the following steps: step 1, flattening reactor core power distribution to determine an enrichment degree gradient and partitions; 2, designing structures of a fuel assembly, a safety rod assembly, an adjusting rod assembly and a compensation rod assembly and a control rod lifting strategy; step 3, determining radial and axial sizes and power density of the reactor core; step 4, reactor core reactivity control design; 5, designing the value of the single-beam control rod; and step 6, irradiation pore channel design. According to the nuclear reactor, high-power-level and long-life reactor core energy output can be achieved by means of nuclear fuel proliferation of the lead-bismuth fast reactor, and through the arrangement of the irradiation hole channels, the transmutation of minor actinide nuclides and long-life fission products, production of various isotopes, irradiation tests of related materials such as fuel elements and assemblies and the like are conducted by means of the high fast neutron fluence rate of the irradiation hole channels.

The invention relates to a fluorination-electrolysis synergistic process applied to post-treatment of a metal spent fuel, which is characterized in that fluorine gas reacts with the pretreated metal spent fuel under a high-temperature condition, uranium, plutonium and a small amount of fluorinated volatile fission products in the spent fuel are converted into gaseous fluoride to be separated and transferred; and the uranium-plutonium alloy is further prepared by using technologies such as condensation trapping and gaseous fluoride reduction. Meanwhile, fluorinated residues containing a large amount of high-radioactivity and high-heat-release fission elements and minor actinide elements are subjected to electrolytic separation through a villiaumite system, and separation and recovery of the minor actinide elements are achieved. The regeneration and reforming preparation of the metal fuel can be realized on the basis of alloy ingots obtained by a gaseous fluoride reduction process and actinide metal alloys obtained by molten salt electrolysis through injection casting supplementary materials. Compared with the prior art, efficient recovery of uranium and plutonium in the metal spent fuel and deep separation and recovery of minor actinide elements are achieved, the process is simple, and the treatment time is short.

Cryogenic granulation, in the conventional way, is carried out on an aqueous suspension comprising one or more oxide powders, which is a preparation that can be a source of splashing and does not completely eliminate the risks.SOLUTION: The invention relates to a process for the manufacture of a powder comprising one or more oxides chosen from uranium oxide UO2, plutonium oxide PuO2 and oxides of minor actinides, the minor actinides being chosen from americium, neptunium and curium, comprising the following steps: a) cryogenic granulation of an aqueous solution comprising cations chosen from uranium-based cations, plutonium-based cations and minor actinide-based cations; b) freeze-drying of the granules obtained in step a); and c) calcining of the granules obtained from step b). An application of the invention is the manufacture of nuclear fuels or blankets filled with minor actinides.SELECTED DRAWING: None

A method for preparing a powder including one or more oxides selected from uranium oxide UO2, plutonium oxide PuO2 and minor actinide oxides, the minor actinides being selected from americium, neptunium and curium, including steps of: a) cryogenic granulation of an aqueous solution comprising cations selected from uranium-based cations, plutonium-based cations, and minor actinide-based cations; b) freeze-drying the granules obtained in a); and c) calcining the granules obtained from b). The method can be used to manufacture nuclear fuels or blankets charged with minor actinide(s).

The application belongs to the technical field of extraction separation, and particularly relates to an OE-DAPhen ligand, a preparation method and application thereof. The application develops a novel DAPhen ligand through specific structure design from the design of a ligand molecular structure. The separation factor (SF) of the OE-DAPhen ligand for lanthanide and actinide elements is more than 400, and the OE-DAPhen ligand exhibits excellent separation performance. The application provides a new perspective for in-depth understanding of lanthanide and actinide separation mechanism, and provides technical support for establishing an advanced spent nuclear fuel reprocessing system and realizing efficient utilization of minor actinide elements. Eu / Am ).

A set of salt compositions containing thorium tetrachloride, for use in molten salt nuclear reactors, is disclosed. The first subset embodiments disclosed involve mixtures of ThCl4 with alkali chlorides NaCl, KCl, and RbCl, alkaline earth chlorides MgCl2, CaCl2, or mixtures thereof, in different proportions. The most useful composition ranges are specified. A second subset of embodiments further includes non-thorium actinide chlorides such as UCl3, UCl4, PuCl3, and the minor actinide trichlorides. The most preferred composition domains are also provided for this subset of embodiments, and were chosen to fit within a design envelope constrained by melting point, boiling point, viscosity, and fission product retention requirements. Additionally, the composition space includes embodiments which are useful in reactors intended to breed new fuel or instead to burn synthetic transuranic elements. In all cases, the presence of ThCl4 confers reduced corrosivity towards engineering alloys and a reduced tendency to degrade ceramics in nuclear reactor environments, compared to salts with a similar design envelope but without ThCl4.

The present invention relates to a method for preparing a powder comprising one or more oxides selected from uranium oxide UO2, plutonium oxide PuO2 and oxides of minor actinides selected from americium, neptunium and curium, said one or more oxides comprising one or more oxides selected from uranium oxide UO2, plutonium oxide PuO2 and oxides of minor actinides selected from uranium oxide UO2, plutonium oxide PuO2 and curium. The method comprises the steps of: a) subjecting an aqueous solution comprising cations selected from uranium-based cations, plutonium-based cations and minor actinide-based cations to low temperature granulation; b) freeze-drying the particles obtained in the step a); and c) calcining the particles obtained from b). Applications: the manufacture of nuclear fuels or claddings loaded with minor actinides.

The invention relates to a process for preparing a powder comprising one or more oxides selected from uranium oxide UO2, plutonium oxide PuO2 and minor actinide oxides, the minor actinides being selected from americium, neptunium and curium, comprising the steps of: a) cryogenic granulation of an aqueous solution comprising cations selected from uranium-based cations, plutonium-based cations and minor actinide-based cations; b) freeze-drying of the granules obtained in a); etc.; calcination of the granules from b). Applications: manufacture of nuclear fuels or blankets loaded with minor actinide(s).

A method of partitioning minor actinides includes directing a minor actinide aqueous solution into an actinide partitioning unit, the minor actinide aqueous solution comprising americium and curium in an aqueous solvent and the americium and the curium are each in a first oxidation state, directing a selective extracting solution into the actinide partitioning unit, wherein the selective extracting solution comprises an organic neutral extractant, an phase modifier, a hydrocarbon diluent, and sodium bismuthate, contacting the minor actinide aqueous solution with the selective extracting solution such that the curium binds with the selective extracting solution to form an organic phase curium solution and the sodium bismuthate induces an oxidation state increase in the americium from the first oxidation state to a second oxidation state, wherein the americium in the second oxidation state remains bound with the minor actinide aqueous solution, thereby partitioning the americium and the curium, and collecting the americium.

To provide a nuclear transmutation method capable of improving a nuclear transmutation amount of minor actinoids (MA) using a fast reactor.SOLUTION: A nuclear transmutation method for MA includes: a step of performing processing of separating MA from high-level radioactive liquid waste being waste liquid obtained by separating U and Pu from a liquid solution of spent nuclear fuel and obtaining a first radioactive composition containing MA; a step of adding U to the first radioactive composition to obtain a second radioactive composition; a step of obtaining an oxide solid solution of MA and U from the second radioactive composition; a storage step of allowing high heat-generating MA contained in the oxide solid solution to decay; a step of producing fuel containing core fuel, radial blanket fuel, upper axial blanket fuel, and lower axial blanket fuel by using the oxide solid solution after storage; and a step of loading the produced fuel into the core of a fast reactor and performing nuclear transmutation of MA contained in the fuel.SELECTED DRAWING: Figure 1