Treatment method for volume reduction of spent uranium catalyst
US-10643758-B2 · May 5, 2020 · US
US9305672B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-9305672-B2 |
| Application number | US-201414291980-A |
| Country | US |
| Kind code | B2 |
| Filing date | May 30, 2014 |
| Priority date | May 30, 2014 |
| Publication date | Apr 5, 2016 |
| Grant date | Apr 5, 2016 |
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A method of immobilizing a radioisotope and vitrified chemically bonded phosphate ceramic (CBPC) articles formed by the method are described. The method comprises combining a radioisotope-containing material, MgO, a source of phosphate, and optionally, a reducing agent, in water at a temperature of less than 100° C. to form a slurry; curing the slurry to form a solid intermediate CBPC article comprising the radioisotope therefrom; comminuting the intermediate CBPC article, mixing the comminuted material with glass frits, and heating the mixture at a temperature in the range of about 900 to about 1500° C. to form a vitrified CBPC article comprising the radioisotope immobilized therein.
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The embodiments of the invention in which an exclusive property or privilege is claimed are defined as follows: 1. A method of immobilizing a radioisotope comprising the steps of: (a) combining a radioisotope-containing material, MgO, a source of phosphate, and optionally, a reducing agent, in water at a temperature of less than 100° C. to form a slurry; (b) curing the slurry to form an intermediate chemically bonded phosphate ceramic (CBPC) article comprising the waste material therefrom; (c) comminuting the intermediate ceramic into fine particles; (d) mixing the fine particles of CBPC with borosilicate glass frits; and (e) heating the mixture resulting from step (d) at a temperature in the range of about 900 to about 1500° C. to form a vitrified CBPC article comprising the radioisotope immobilized therein. 2. The method of claim 1 wherein the radioisotope-containing material comprises at least one radioisotope selected from the group consisting of a radioisotope of Cs, Sr, and I. 3. The method of claim 1 wherein the radioisotope-containing material comprises a radioisotope of Tc and the slurry comprises a reducing agent for reducing Tc(VII) to Tc(IV). 4. The method of claim 3 wherein the reducing agent comprises Sn(II). 5. The method of claim 1 wherein the radioisotope-containing material comprises a solid material, a liquid material, or a combination thereof. 6. The method of claim 1 wherein the radioisotope-containing material comprises a radioactive waste sludge. 7. The method of claim 1 wherein the step of heating is performed at a temperature in the range of about 1100 to about 1300° C. 8. The method of claim 1 wherein the source of phosphate comprises KH 2 PO 4 . 9. The method of claim 1 wherein the slurry is prepared with a molar ratio of MgO-to-KH 2 PO 4 -to-water of about 1:1:5. 10. The method of claim 1 wherein the slurry further comprises one or more additional an oxide or salt of an element selected from the group consisting of an alkaline earth metal, a transition metal, a main group metal, a lanthanide, an actinide, and a metalloid. 11. The method of claim 1 wherein the slurry further comprises one or more extenders selected from fly ash, wollastonite, and silica sand.
for glass comprising or including particular isotopes · CPC title
Glass-ceramics matrix · CPC title
in an inorganic matrix, e.g. clays, zeolites · CPC title
Waste material, e.g. to be disposed of · CPC title
based on phosphates {, e.g. hydroxyapatite} · CPC title
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