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.

Composite gel particles with an ammonium diuranate matrix phase and a phenolic resin phase incorporated within the ammonium diuranate matrix phase are produced from a first solution comprising uranyl nitrate, a phenol, and optionally formaldehyde, wherein the uranyl nitrate and the phenol are present in a ratio ranging from 2:1 to 25:1; and a second solution comprising hexamethylenetetramine and urea. The first solution and the second solution are mixed, and drops of the resulting mixture into a heated second liquid which is immiscible with the mixed solution. Heat from the second liquid causes the hexamethylenetetramine to decompose to form ammonia, which reacts with the uranyl nitrate to cause each of the drops to form an ammonium diuranate gel particle. The ammonium diuranate gel particles are collected. The ammonium diuranate gel particles include the phenolic resin phase within the ammonium diuranate matrix phase, where the phenolic resin phase is formed by reaction between the phenol and formaldehyde. The first solution may include uranyl nitrate, the phenol, and formaldehyde, and the formaldehyde and the phenol may react to form the phenolic resin phase prior to mixing the first solution and the second solution. The first solution may be free of formaldehyde, and heat from the second liquid may causes the hexamethylenetetramine to decompose to form formaldehyde in situ; so that the formaldehyde and the phenol react to form the phenolic resin phase while the ammonia reacts with the uranyl nitrate.

What is provided is stannous oxide having an ?-ray emission amount of 0.002 cph/cm.sup.2 or less after heating in an atmosphere at 100? C. for 6 hours. Tin containing lead as an impurity is dissolved in a sulfuric acid aqueous solution to prepare a tin sulfate aqueous solution, and lead sulfate is precipitated in the aqueous solution and removed. While stirring the tin sulfate aqueous solution from which lead sulfate has been removed, a lead nitrate aqueous solution containing lead having an ?-ray emission amount of 10 cph/cm.sup.2 or less is added to cause lead sulfate to be precipitated in the tin sulfate aqueous solution, and simultaneously the tin sulfate aqueous solution is circulated while removing the lead sulfate from the aqueous solution. A neutralizing agent is added to the tin sulfate aqueous solution to collect stannous oxide.

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.

A process for producing a titanium-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 titanium source to provide a TiMo composition. The TiMo composition can be pH adjusted with a base to precipitate a plurality of TiMo particulates.

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.

A method of preparing silicon carbide according to the present invention includes reacting a silicon-containing compound with carbon dioxide, wherein a reducing agent is optionally used.

Methods and systems that remove impurities from phosphogypsum (PG), including from radium and heavy metal salts, and produce gypsum binders and products. In one embodiment, PG is reacted with a chloride solution in an acidic environment under mechanical manipulation and/or heat followed by galvanic and/or zeolite absorption removal of impurities.

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.

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.3UCl.sub.4NaCl or UCl.sub.3NaCl fuel salt composition from UCl.sub.4NaCl.