Injectable sacrificial material systems and methods to contain molten corium in nuclear accidents

US2022157478A1 · US · A1

Patent metadata
FieldValue
Publication numberUS-2022157478-A1
Application numberUS-202217665719-A
CountryUS
Kind codeA1
Filing dateFeb 7, 2022
Priority dateJul 25, 2018
Publication dateMay 19, 2022
Grant date

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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

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Systems and methods for injecting a carbonate-based sacrificial material into a nuclear reactor containment for containment of molten corium in severe nuclear reactor accidents are disclosed. Molten corium can be quickly cooled and solidified by the endothermic decomposition of the sacrificial material.

First claim

Opening claim text (preview).

What is claimed is: 1 . A system for delivering a carbonate-based material within a nuclear reactor containment, comprising: a nuclear reactor contained within the nuclear containment; a storage tank containing a mass of the carbonate-based material; and a gravity fluid delivery system for transporting the carbonate-based material within the nuclear containment vessel. 2 . The system of claim 1 , wherein the carbonate-based material is a carbonate-based material selected from a group consisting essentially of alkaline, alkali, transition metal carbonates and mixtures thereof. 3 . The system of claim 1 , wherein the carbonate-based material is an alkaline carbonate-based material selected from a group consisting essentially of calcium carbonate (CaCO 3 ), magnesium carbonate (MgCO 3 ), dolomite [CaMg(CO 3 ) 2 ] and mixtures thereof. 4 . The system of claim 1 , wherein the carbonate-based material is an alkali carbonate-based material selected from a group consisting essentially of sodium carbonate (Na 2 CO 3 ), potassium carbonate (K 2 CO 3 ) and mixtures thereof. 5 . The system of claim 1 , wherein the carbonate-based material is a transition metal carbonate-based material selected from a group consisting essentially of iron carbonate (FeCO 3 ), manganese carbonate (MnCO 3 ) and mixtures thereof. 6 . A method for containing corium in a nuclear reactor accident within a reactor containment, comprising: delivering and contacting a carbonate-based material with molten corium; wherein the carbonate-based material is delivered by a non-pressurized, passive delivery system using gravity to deliver the carbonate-based material to the molten corium. 7 . The method of claim 6 , wherein the carbonate-based material is selected from a group consisting essentially of alkaline, alkali, transition metal carbonates and the mixtures thereof. 8 . The method of claim 6 , wherein the carbonate-based material is an alkaline carbonate-based material selected from a group consisting essentially of calcium carbonate (CaCO 3 ), magnesium carbonate (MgCO 3 ), dolomite [CaMg(CO 3 ) 2 ] and mixtures thereof. 9 . The method of claim 6 , wherein the carbonate-based material is an alkali carbonate-based material selected from a group consisting essentially of sodium carbonate (Na 2 CO 3 ), potassium carbonate (K 2 CO 3 ) and mixtures thereof. 10 . The method of claim 6 , wherein the carbonate-based material is a transition metal carbonate-based material selected from a group consisting essentially of iron carbonate (FeCO 3 ), manganese carbonate (MnCO 3 ) and mixtures thereof. 11 . The method of claim 6 , wherein the carbonate-based material is prepared by a method selected from a group consisting essentially of crushing, grinding and palletization to form a grain size ranging from sub-millimeters to 100 centimeters. 12 . The method of claim 11 , wherein the grain size is chosen to control carbonate decomposition rate and injectivity of the carbonate-based material. 13 . The method of claim 6 , wherein the carbonate-based material comprises hematite (Fe 2 O 3 ) to convert metallic zirconium to zirconium oxide by reaction during corium cooling and solidification, thus eliminating or minimizing hydrogen gas generation from metallic zirconium. 14 . The method of claim 13 , wherein the hematite (Fe 2 O 3 ) percentage of the carbonate-based material is determined by the mass fraction of metallic zirconium initially contained in corium melt.

Assignees

Inventors

Classifications

  • Nuclear fission reactors · CPC title

  • Non-aqueous processes · CPC title

  • Emergency cooling arrangements; Removing shut-down heat · CPC title

  • G21C9/016Primary

    Core catchers · CPC title

  • Emergency protection arrangements structurally associated with the reactor {, e.g. safety valves provided with pressure equalisation devices}(emergency cooling arrangements G21C15/18) · CPC title

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What does patent US2022157478A1 cover?
Systems and methods for injecting a carbonate-based sacrificial material into a nuclear reactor containment for containment of molten corium in severe nuclear reactor accidents are disclosed. Molten corium can be quickly cooled and solidified by the endothermic decomposition of the sacrificial material.
Who is the assignee on this patent?
Nat Tech & Eng Solutions Sandia Llc
What technology area does this patent fall under?
Primary CPC classification G21C9/016. Mapped technology areas include Physics.
When was this patent published?
Publication date Thu May 19 2022 00:00:00 GMT+0000 (Coordinated Universal Time) (A1). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 8 related publications on this page (citations in our corpus or others sharing the same primary CPC).