# US 9,437,336 B2 · Isotope-specific separation and vitrification using ion-specific media > Agents: this data is available as JSON from the patentgrep API and MCP server — see https://patentgrep.com/llms.txt - Number: US 9,437,336 B2 - Document ID: US9437336B2 - Status: Granted - Kind: B2 - Application number: 13/043,843 - Filed: 2011-03-09 - Published: 2011-09-15 - Granted: 2016-09-06 - Earliest claimed: 2010-03-09 - Assignees: Kurion, Inc. - Applicants: Mark S. Denton - Inventors: Mark S. Denton - Web page: https://patentgrep.com/patent/US9437336B2 ## CPC - G21F 9/125: {by solvent extraction} - G21F 9/02: Treating gases - G21F 9/12: by absorption; by adsorption; by ion-exchange - G21F 9/16: by fixation in stable solid media {(G21F9/305 takes precedence)} - G21F 9/162: {in an inorganic matrix, e.g. clays, zeolites} - G21F 9/305: {Glass or glass like matrix (C03B5/005 takes precedence; compositional aspects C03C)} - Y02E 30/30: Nuclear fission reactors - G21F: PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR (radiation protection by pharmaceutical means A61K8/00, A61Q17/04; in cosmonautic vehicles B64G1/54; combined with a reactor G21C11/00; combined with X-ray tubes H01J35/16; combined with X-ray apparatus H05G1/02) - Y02E: REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION ## Abstract Apparatuses, processes and methods for the separation, isolation, or removal of specific radioactive isotopes from liquid radioactive waste, these processes and methods employing isotope-specific media (ISM). In some embodiments, the processes and methods further include the vitrification of the separated isotopes, generally with the ISM; this isotope-specific vitrification (ISV) is often a step in a larger scheme of preparing the radioactive isotopes for long-term storage or other disposition. A variety of ISM are disclosed. ## Claims ### Claim 1 A method for processing radioactive waste comprising: separating radioactive waste material into liquid waste with radioactive isotopes and solid waste; passing the liquid waste with radioactive isotopes through an inlet line of an ion exchange column through a dip tube oriented in a generally vertical direction within the ion exchange column, wherein the liquid waste is dispersed throughout the ion exchange column by a distribution ring attached to the dip tube and suspended within the ion exchange column in a generally horizontal orientation, wherein the distribution ring comprises a plurality of distribution holes that direct the liquid waste in a downward direction towards a bottom end of the ion exchange column, and wherein the dispersed liquid waste is pushed through media contained within the ion exchange column for capturing one or more of the radioactive isotopes from the liquid waste; pushing the liquid waste with a reduced amount of the radioactive isotopes out of the ion exchange column through an outlet line; and vitrifying the media and captured radioactive isotopes contained in the ion exchange column into a glass matrix wherein the dip tube and the distribution ring are both encased within the glass matrix. ### Claim 2 (depends on 1) The method of claim 1 wherein the ion exchange column comprises a first column containing a first media for capturing a first group of radioactive isotopes and further comprising: passing the liquid waste from the outlet line of the first column into a second inlet line of a second column, through a dip tube into the second column, and pushing the liquid waste through a second media contained within the second column for capturing a second different group of radioactive isotopes from the liquid waste; and pushing the liquid waste with a reduced amount of the second different group of radioactive isotopes out through a second outlet line of the second column. ### Claim 3 (depends on 2) The method of claim 2 further comprising: passing the liquid waste from the second outlet line into a third inlet line of a third column, through a dip tube into the third column, and pushing the liquid waste through a third media contained within the third column for capturing a third different group of radioactive isotopes from the liquid waste; and pushing the liquid waste with a reduced amount of the third different group of radioactive isotopes out through a third outlet line of the third column. ### Claim 4 (depends on 3) The method of claim 3, wherein: the first media is configured to capture cesium radioactive isotopes; the second media is configured to capture strontium radioactive isotopes; and the third media is configured to capture technetium radioactive-isotopes. ### Claim 5 (depends on 1) The method of claim 1 further comprising, after passing the liquid waste through the ion exchange column, recycling the liquid waste to a nuclear reactor. ### Claim 6 (depends on 1) The method of claim 1 wherein the one or more radioactive isotopes include at least one isotope of cesium. ### Claim 7 (depends on 1) The method of claim 1 wherein the one or more radioactive isotopes include at least one isotope of strontium. ### Claim 8 (depends on 7) The method of claim 7 wherein the media comprises hydroxyapatite. ### Claim 9 (depends on 7) The method of claim 7 wherein the media comprises microspheres that include hydroxyapatite. ### Claim 10 (depends on 1) The method of claim 1 wherein the one or more radioactive isotopes include at least one isotope of technetium. ### Claim 11 (depends on 1) The method of claim 1 wherein the one or more radioactive isotopes include at least one isotope of iodine. ### Claim 12 (depends on 1) The method of claim 1 wherein the one or more radioactive isotopes include at least one isotope selected from the group consisting of nickel, cobalt, and lead. ### Claim 13 (depends on 1) The method of claim 1 wherein the media comprises glass beads fabricated from a mixture of sodium, calcium and boron, the glass beads are mixed with potassium phosphate solution, and the sodium, calcium, and boron react with the potassium phosphate solution to form a hydroxyapatite layer on the glass beads. ### Claim 14 (depends on 1) The method of claim 1 wherein the dip tube and the distribution ring are both formed from a ceramic material. ### Claim 15 (depends on 1) The method of claim 1 wherein the dip tube and the distribution ring are both formed from a porous graphite material. ### Claim 16 (depends on 1) The method of claim 1 wherein the ion exchange column comprises a Herschelite material. ### Claim 17 (depends on 1) The method of claim 1 wherein the ion exchange column comprises an outer steel layer and an inner graphite layer, and wherein vitrifying the media comprises inductively heating the media using the inner graphite layer of the ion exchange column as a susceptor. ### Claim 18 (depends on 17) The method of claim 17 wherein the inner graphite layer forms a crucible for melting the media. ### Claim 19 (depends on 17) The method of claim 17 wherein the ion exchange column further comprises a middle layer of insulation located between the outer steel layer and the inner graphite layer. ### Claim 20 (depends on 1) The method of claim 1, wherein the distribution ring is suspended above the bottom end of the ion exchange column. ### Claim 21 (depends on 20) The method of claim 20, wherein both the inlet line and the outlet line are located at a top end of the ion exchange column, and wherein the dispersed liquid waste is pushed through the media from the bottom end of the ion exchange column to the top end of the ion exchange column.