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.

What is provided is stannous oxide having an α-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 α-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.

The invention provides a low alpha dose barium sulfate particle having a silica content of 0.6% by weight or less, an average particle diameter of 1 μm or less, a sulfur content of 10 ppm or less, and an alpha dose of 0.07 cph/cm.sup.2 or less.

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.

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 Mo that decays to produce .sup.99mTc.

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.

The invention provides a low alpha dose barium sulfate particle having a silica content of 0.6% by weight or less, an average particle diameter of 1 m or less, a sulfur content of 10 ppm or less, and an alpha dose of 0.07 cph/cm.sup.2 or less.

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.

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.

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.