Method for process for producing fully ceramic microencapsulated fuels containing tristructural-isotropic particles with a coating layer having higher shrinkage than matrix

US11715571B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-11715571-B2
Application numberUS-202117216678-A
CountryUS
Kind codeB2
Filing dateMar 30, 2021
Priority dateAug 7, 2015
Publication dateAug 1, 2023
Grant dateAug 1, 2023

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  1. Title

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  2. Abstract

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  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

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Abstract

Official abstract text for this publication.

The present invention relates to a method for preparing a fully ceramic capsulated nuclear fuel material containing three-layer-structured isotropic nuclear fuel particles coated with a ceramic having a composition which has a higher shrinkage than a matrix in order to prevent cracking of ceramic nuclear fuel, wherein the three-layer-structured nuclear fuel particles before coating is included in the range of between 5 and 40 fractions by volume based on after sintering. More specifically, the present invention provides a composition for preparing a fully ceramic capsulated nuclear fuel containing three-layer-structured isotropic particles coated with the substance which includes, as a main ingredient, a silicon carbine derived from a precursor of the silicon carbide wherein a condition of ΔL c >ΔL m at normal pressure sintering is created, where the sintering shrinkage of the coating layer of the three-layer-structured isotropic nuclear fuel particles is ΔL c and the sintering shrinkage of the silicon carbide matrix is ΔL m ; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.

First claim

Opening claim text (preview).

What is claimed is: 1. A method for preparing a fully ceramic capsulated nuclear fuel material, comprising: (i) preparing a first mixture of a coating layer composition including a silicon carbide precursor; (ii) coating three-layer-structured isotropic nuclear fuel particles by using the first mixture; (iii) preparing a second mixture of a silicon carbide matrix phase; (iv) preparing a third mixture by mixing the coated three-layer-structured isotropic nuclear fuel particles with the second mixture of the silicon carbide matrix phase; (v) preparing a shaped body by using the third mixture; and (vi) performing pressureless sintering of the shaped body, wherein, when a shrinkage of the coating layer of the three-layer-structured isotropic nuclear fuel particles during the pressureless sintering process is given as ΔL C , and when a shrinkage of the silicon carbide matrix phase during the sintering process is given as ΔL m , a condition of ΔL C >ΔL m is satisfied when performing the pressureless sintering, wherein the silicon carbide precursor is shifted to silicon carbide in order to densify the coating layer during the pressureless sintering process such that the shrinkage of the coating layer is greater than the shrinkage of the silicon carbide matrix phase. 2. The method of claim 1 , wherein a sintering temperature range during the pressureless sintering process is 1700-1800° C. 3. The method of claim 2 , wherein a holding time at a maximum temperature during the pressureless sintering process corresponds to 0.5-4 hours, and wherein the sintering atmosphere corresponds to argon. 4. The method of claim 1 , wherein, in the step of preparing a partially sintered material, the preparation is carried out at a heating speed within a range of 0.1-1° C./min in order to control cracking in the shaped body caused by a discharge of gas, the discharged gas being a by-product of the thermal decompression of the silicon carbide precursor. 5. The method of claim 1 , wherein, in the step of (vi) performing pressureless sintering of the shaped body, the atmosphere consists of ambient air starting from ambient temperature to 200° C. for cross-linking of the silicon carbide precursor, and wherein the atmosphere consists of argon gas starting from 200° C. to a temperature range of 800-1400° C. in order to prevent oxidation of silicon carbide.

Assignees

Inventors

Classifications

  • G21C3/626Primary

    Coated fuel particles · CPC title

  • based on silicon carbide · CPC title

  • Milling · CPC title

  • Drying, e.g. freeze-drying, spray-drying, microwave or supercritical drying · CPC title

  • by wet chemical techniques · CPC title

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What does patent US11715571B2 cover?
The present invention relates to a method for preparing a fully ceramic capsulated nuclear fuel material containing three-layer-structured isotropic nuclear fuel particles coated with a ceramic having a composition which has a higher shrinkage than a matrix in order to prevent cracking of ceramic nuclear fuel, wherein the three-layer-structured nuclear fuel particles before coating is included …
Who is the assignee on this patent?
Univ Seoul Ind Coop Found, Kepco Nuclear Fuel Co Ltd
What technology area does this patent fall under?
Primary CPC classification G21C3/626. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Aug 01 2023 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 3 related publications on this page (citations in our corpus or others sharing the same primary CPC).