Patent Number: 
Section: claims

1. A process for treating radioactive isotopes in liquid, the method comprising:mixing glass beads comprising sodium, calcium and boron with a potassium phosphate solution, wherein the sodium, calcium, and boron react with the potassium phosphate solution to form a hydroxyapatite layer that covers the glass beads;placing hydroxyapatite microspheres comprising the glass beads covered with the hydroxyapatite layer in an ion exchange column;passing the liquid with radioactive isotopes through the ion exchange column of media comprising the hydroxyapatite microspheres for capturing one or more of the radioactive isotopes from the liquid, wherein passing the liquid with radioactive isotopes through the ion exchange column comprises passing said liquid through a dip tube oriented in a generally vertical direction and into a distribution ring attached to the dip tube and suspended within the ion exchange column in a generally horizontal orientation, and wherein the distribution ring comprises a plurality of distribution holes that direct the liquid radioactive waste in a downward direction towards a bottom end of the ion exchange column, whereby as the liquid passes through and near the media contained within the ion exchange column, the one or more radioactive isotopes are separated from the liquid and retained within the ion exchange column by the media; andheating the media and separated radioactive isotopes to form a vitrified waste product, wherein the vitrified waste product contains at least one of the the dip tube and the distribution ring. 2. The process of claim 1, wherein the one or more radioactive isotopes comprise strontium. 3. The process of claim 2, wherein the media include glass-based microspheres. 4. The process of claim 1, wherein the media include Herschelite. 5. The process of claim 1, wherein the media include a surfactant-modified zeolite. 6. The process of claim 1, wherein the liquid with radioactive isotopes is passed through multiple columns, each column containing media for capturing at least one radioactive isotope different from one or more radioactive isotopes separated in the other columns. 7. The process of claim 1, wherein the potassium phosphate solution also comprises potassium hydroxide. 8. A process for treating radioactive isotopes, the process comprising:pyrolizing solid radioactive waste;expelling gas and vapor that result from pyrolizing the solid radioactive waste, wherein the expelled gas and vapor comprise one or more radioactive isotopes;condensing the expelled gas and vapor to form liquid radioactive waste;mixing the liquid radioactive waste with a plurality of microspheres contained in an ion exchange column to transfer one or more radioactive isotopes from the liquid radioactive waste to the plurality of microspheres;responsive to mixing the liquid radioactive waste, pass the waste through a dip tube oriented in a generally vertical direction and into a distribution ring attached to the dip tube and suspended within the ion exchange column in a generally horizontal orientation, and wherein the distribution ring comprises a plurality of distribution holes that direct the liquid radioactive waste in a downward direction towards a bottom end of the ion exchange column;pumping the liquid waste out of the column; andheating the plurality of microspheres with the transferred radioactive isotopes while located inside of the column to form a vitrified waste product, wherein the vitrified waste product contains at least one of the dip tube and the distribution ring. 9. The process of claim 8, wherein the ion exchange column includes a graphite inner layer that acts as a susceptor for inductive heating of the plurality of microspheres. 10. The process of claim 8, wherein the plurality of microspheres comprise glass beads mixed with a potassium phosphate solution to form hydroxyapatite microspheres. 11. The process of claim 8, wherein pyrolizing the solid radioactive waste comprises forming molten radioactive material, and wherein the process further comprises vitrifying the molten radioactive material separately from the plurality of microspheres. 12. The process of claim 11, wherein the ion exchange column is configured to separate and isolate radioactive isotopes that are not vitrified with the molten radioactive material.