Abstract: An electrical cable has an elongate electrical conductor having, in cross section, a plurality of mutually electrically insulated segments having a plurality of metallic wires, at least one of the metallic wires in at least one of the segments being covered by at least one electrically insulating layer. The electrically insulating layer is obtained on the basis of a composition A having at least one acrylic polymer and at least one transition metal salt.

Abstract: The invention is directed to systems and methods for making non-hollow, non-fragmented spherical metal or metal alloy particles using diffusion dryers.

Abstract: The invention relates to a process for producing 228Th from a natural thorium salt, which comprises in succession: a) the separation of the radium from the other radioelements present in this salt, by at least one coprecipitation of the radium by barium sulphate, this coprecipitation comprising: i) the addition of sulphuric acid and a barium salt to an aqueous solution of said natural thorium salt in order to form a barium-radium sulphate coprecipitate and ii) the separation of the coprecipitate from the medium in which it has formed; b) the extraction of the thorium 228 coming from the decay of radium 228 from the coprecipitate thus separated; and, optionally c) the purification and concentration of the 228Th thus extracted. Applications: manufacture of radiopharmaceutical products useful in nuclear medicine, in particular in radioimmunotherapy for the treatment of cancers and AIDS.

Abstract: The invention relates to a process for producing 228Th from a natural thorium salt, which comprises in succession: a) the separation of the radium from the other radioelements present in this salt, by at least one coprecipitation of the radium by barium sulphate, this coprecipitation comprising: i) the addition of sulphuric acid and a barium salt to an aqueous solution of said natural thorium salt in order to form a barium-radium sulphate coprecipitate and ii) the separation of the coprecipitate from the medium in which it has formed; b) the extraction of the thorium 228 coming from the decay of radium 228 from the coprecipitate thus separated; and, optionally c) the purification and concentration of the 228Th thus extracted. Applications: manufacture of radiopharmaceutical products useful in nuclear medicine, in particular in radioimmunotherapy for the treatment of cancers and AIDS.

Abstract: A process for facilitating the removal of impurities e.g. radionuclides, such as uranium and thorium, and/or one or more of their radionuclide daughters, from titaniferous material includes contacting the titaniferous material with one or more reagents at an elevated temperature selected to enhance the accessibility of at least one of the radionuclide daughters in the titaniferous material. The reagent(s) may be a glass forming reagent and is selected to form a phase at the elevated temperature which disperses onto the surfaces of the titaniferous material and incorporates the radionuclides and one or more radionuclide daughter. The titaniferous material may be, e.g., ilmenite, reduced ilmenite, altered ilmenite or synthetic rutile.

Abstract: A process for facilitating the removal of impurities e.g. radionuclides, such as uranium and thorium, and/or one or more of their radionuclide daughters, from titaniferous material includes contacting the titaniferous material with one or more reagents at an elevated temperature selected to enhance the accessibility of at least one of the radionuclide daughters in the titaniferous material. The reagent(s) may be a glass forming reagent and is selected to form a phase at the elevated temperature which disperses onto the surfaces of the titaniferous material and incorporates the radionuclides and one or more radionuclide daughters. The titaniferous material may be, e.g., ilmenite, reduced ilmenite, altered ilmenite or synthetic rutile.

Abstract: In the pyrochemical reduction of uranium dioxide or other actinide metal oxides by reaction with magnesium, magnesium oxide byproduct is produced. The use of a salt flux comprising magnesium chloride and a rare earth element trichloride such as neodymium chloride is disclosed. The neodymium chloride reacts with magnesium oxide to form magnesium chloride and neodymium oxychloride. The resulting magnesium chloride-neodymium oxychloride salt mixture can readily be subjected to electrolysis to regenerate magnesium and neodymium chloride for reuse in the pyrochemical reduction process. Other uses of the magnesium chloride-neodymium chloride salt flux are also proposed.

Abstract: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800.degree. C. to about 850.degree. C. to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel.

Abstract: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800.degree. C. to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein.