Composite glass, especially for a vehicle
US-2024391215-A1 · Nov 28, 2024 · US
US11587693B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-11587693-B2 |
| Application number | US-202016859465-A |
| Country | US |
| Kind code | B2 |
| Filing date | Apr 27, 2020 |
| Priority date | Oct 21, 2019 |
| Publication date | Feb 21, 2023 |
| Grant date | Feb 21, 2023 |
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The present disclosure provides a solidifying method of a radionuclide. The solidifying method of the radionuclide includes operations of: providing a low melting point glass including Bi 2 O 3 , B 2 O 3 , ZnO and SiO 2 ; providing a glass mixture mixing a mixture to be treated containing a hydroxide of radionuclide and BaSO 4 and the low melting point glass; and heating the glass mixture.
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What is claimed is: 1. A solidifying method of a radionuclide, comprising operations of: providing a low melting point glass including Bi 2 O 3 , B 2 O 3 , ZnO and SiO 2 ; providing a glass mixture by mixing a mixture to be treated containing a hydroxide of radionuclide and BaSO 4 , and the low melting point glass; and heating the glass mixture. 2. The solidifying method of the radionuclide of claim 1 , wherein the radionuclide comprises at least one selected from a group consisting of radioisotopes of chromium, cobalt, iron and nickel metals. 3. The solidifying method of the radionuclide of claim 1 , wherein the low melting point glass has a melting point of 440 to 460° C. 4. The solidifying method of the radionuclide of claim 1 , wherein the mixture to be treated is a waste of HyBRID decontamination process. 5. The solidifying method of the radionuclide of claim 1 , wherein the mixture to be treated contains BaSO 4 in an amount of 90% to 97% by weight, based on a total weight of the mixture to be treated. 6. The solidifying method of the radionuclide of claim 1 , wherein the mixture to be treated is included in an amount of 15% to 20% by weight in the glass mixture, based on a total weight of the glass mixture. 7. The solidifying method of the radionuclide of claim 1 , wherein the mixture to be treated and the low melting point glass are provided as powders, respectively. 8. The solidifying method of the radionuclide of claim 7 , wherein the powder of the low melting point glass powder is a powder having a particle size of 0.8 to 1.2 times an average particle size of the powder of the mixture to be treated. 9. The solidifying method of the radionuclide of claim 1 , wherein the operation of heating the glass mixture is performed at 500 to 550° C. 10. The solidifying method of the radionuclide of claim 1 , wherein the low melting point glass is obtained by including operations of: mixing Bi 2 O 3 , B 2 O 3 , ZnO and SiO 2 powder particles; melting the mixed powder; cooling the molten material; and drying the cooled material. 11. The solidifying method of the radionuclide of claim 10 , wherein the operation of mixing Bi 2 O 3 , B 2 O 3 , ZnO and SiO 2 powder particles is performed by mixing 32 to 38 mol % of Bi 2 O 3 , 25 to 30 mol % of B 2 O 3 , 29 to 35 mol % of ZnO, and 5 to 7 mol % of SiO 2 , based on the total number of moles of the powder. 12. The solidifying method of the radionuclide of claim 10 , further comprising an operation of: pulverizing such that the average particle size of the low melting point glass powder is 180 to 220 mesh.
Production of cement, e.g. improving or optimising the production methods; Cement grinding · CPC title
containing zinc · CPC title
Glass or glass like matrix (C03B5/005 takes precedence; compositional aspects C03C) · CPC title
of glass-forming waste materials (disposal or transformation of solid waste in general B09B; treatment of radioactive waste G21F9/00) · CPC title
the non-glass component being in the form of particles or flakes · CPC title
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