A method for preparing, in the internal volume of at least one channel, a monolithic support on which uranyl cations are immobilised. The method comprises: (a) activating the inner surface of the channel(s); (b) introducing, into the internal volume of the channel(s), a polymerisation solution comprising: a monomer comprising a phosphate group, at least one crosslinking agent, several solvents, and a radical polymerisation initiator; (c) polymerising the polymerisation solution; (d) rinsing the monolithic support obtained in step (c); and (e) contacting the monolithic support previously rinsed, with a solution comprising uranyl cations. A method for capturing proteins that selectively bind uranium by means of a monolithic support prepared by the above-mentioned method, as well as to a method for recovering proteins that selectively bind uranium with the capture method.

A method for synthesising metal oxide nanoparticles. The method comprises mixing, to provide a reaction mixture, a precursor solution comprising metal ions with an initiator solution to initiate a nanoparticle precipitation process, and then quenching the precipitation process by adding a quenching agent to the reaction mixture so as to yield a dispersion comprising metal oxide nanoparticles. The resulting metal oxide nanoparticles may have an average diameter of less than 7 nm, for example 5 nm or less.

This invention relates to strontium-phosphate microparticles that incorporate radioisotopes for radiation therapy and imaging.

The present invention relates to a process for sintering a compacted powder of at least one oxide of a metal selected from an actinide and a lanthanide, this process comprising the following successive steps, carried out in a furnace and under an atmosphere comprising an inert gas, dihydrogen and water: (a) a temperature increase from an initial temperature T.sub.I up to a hold temperature T.sub.P, (b) maintaining the temperature at the hold temperature T.sub.P, and (c) a temperature decrease from the hold temperature T.sub.P down to a final temperature T.sub.F, in which the P(H.sub.2)/P(H.sub.2O) ratio is such that: 500<P(H.sub.2)/P(H.sub.2O)≦50 000, during step (a), from T.sub.I until a first intermediate temperature T.sub.i1 between 1000° C. and T.sub.P is reached, and P(H.sub.2)/P(H.sub.2O)≦500, at least during step (c), from a second intermediate temperature T.sub.i2 between T.sub.P and 1000° C., until T.sub.F is reached.

Methods and systems are provided for continuous-flow production of radioisotopes with high specific activity. Radioisotopes with high specific activity produced according to the methods described are also provided. The methods can include causing a liquid capture matrix to contact a target containing a target nuclide; irradiating the target with radiation, ionizing radiation, particles, or a combination thereof to produce the radionuclides that are ejected from the target and into the capture matrix; and causing the liquid capture matrix containing the radionuclides to flow from the target to recover the capture matrix containing the radionuclides with high specific activity. The methods are suitable for the production of a variety of radionuclides. For example, in some aspects the target nuclide is .sup.237Np, and the radionuclide is .sup.238Np that decays to produce .sup.238Pu. In other aspects, the target nuclide is .sup.98Mo, and the radionuclide is .sup.99Mo that decays to produce .sup.99mTc.

Fuel capsules usable in inertial confinement fusion (ICF) reactors have shells made from materials having a diamond (sp.sup.3) lattice structure, including diamond materials in synthetic crystalline, polycrystalline (ordered or disordered), nanocrystalline and amorphous forms. The interior of the shell is filled with a fusion fuel mixture, including any combination of deuterium and/or tritium and/or helium-3 and/or other fusible isotopes.

This disclosure describes systems and methods for synthesizing UCl.sub.3 from UCl.sub.4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl.sub.4, UCl.sub.3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl.sub.3—UCl.sub.4—NaCl or UCl.sub.3—NaCl fuel salt composition from UCl.sub.4—NaCl.

A process for producing a metal-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a metal source to provide a metal-Mo composition. The metal-Mo composition can be pH adjusted with a base to precipitate a plurality of metal-Mo particulates.

Methods for rapid isolation of radionuclides (e.g., .sup.68Ga) produced using a cyclotron and methods for recycling of the parent isotope (e.g., .sup.68Zn) are disclosed. In one version of the method, a solution including a radionuclide (e.g., .sup.68Ga) is created from a target including cations (e.g., .sup.68Zn). The solution including the radionuclide is passed through a first column including a sorbent comprising a hydroxamate resin to adsorb the radionuclide on the sorbent, and the radionuclide is eluted off the sorbent. The cations (e.g., .sup.68Zn) are recovered from a recovery solution that has passed through the first column by passing the recovery solution through a second column including a second sorbent comprising a cation exchange resin.

A process for producing a metal-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a metal source to provide a metal-Mo composition. The metal-Mo composition can be pH adjusted with a base to precipitate a plurality of metal-Mo particulates.