Modeling for fuel element deformation
US-10163534-B2 · Dec 25, 2018 · US
US2023395269A1 · US · A1
| Field | Value |
|---|---|
| Publication number | US-2023395269-A1 |
| Application number | US-202318453317-A |
| Country | US |
| Kind code | A1 |
| Filing date | Aug 22, 2023 |
| Priority date | Aug 27, 2015 |
| Publication date | Dec 7, 2023 |
| Grant date | — |
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A fuel element has a ratio of area of fissionable nuclear fuel in a cross-section of the tubular fuel element perpendicular to the longitudinal axis to total area of the interior volume in the cross-section of the tubular fuel element that varies with position along the longitudinal axis. The ratio can vary with position along the longitudinal axis between a minimum of 0.30 and a maximum of 1.0. Increasing the ratio above and below the peak burn-up location associated with conventional systems reduces the peak burn-up and flattens and shifts the burn-up distribution, which is preferably Gaussian. The longitudinal variation can be implemented in fuel assemblies using fuel bodies, such as pellets, rods or annuli, or fuel in the form of metal sponge and meaningfully increases efficiency of fuel utilization.
Opening claim text (preview).
What is claimed is: 1 . A method of manufacturing a fuel element, the method comprising: providing a cladding; disposing a first fissionable composition within a first end section of an interior volume of the cladding and in thermal transfer contact with an interior surface of the cladding, the first fissionable composition having a first average smear density; and disposing a second fissionable composition within a central section of the interior volume and in thermal transfer contact with the interior surface of the cladding, the second fissionable composition having a second average smear density less than the first average smear density; disposing a third fissionable composition within a second end section of the interior volume of the cladding and in thermal transfer contact with the interior surface of the cladding, the third fissionable composition having a third average smear density greater than the second average smear density. 2 . The method of claim 1 , wherein smear density of the first fissionable composition varies according to a decreasing step function within the first end section and smear density of the second fissionable composition varies according to an increasing step function within the second end section. 3 . The method of claim 1 , wherein the first end section and the second end section are of equal length and the first average smear density is greater than the third average smear density. 4 . The method of claim 1 , wherein smear density of the first fissionable composition, second fissionable composition, and third fissionable composition varies continuously along a length of the fuel element and approximates an inverted Gaussian shape. 5 . The method of claim 1 , wherein smear density varies according to a step function. 6 . The method of claim 1 , wherein the first end of the interior volume of the cladding is proximate a coolant entry point of the cladding and the second end section of the interior volume of the cladding is proximate to a coolant exit point of the cladding. 7 . The method of claim 1 , wherein disposing a first fissionable composition within the first end section of in the interior volume of the cladding comprises disposing a fissionable metal sponge. 8 . The method of claim 1 , wherein disposing a first fissionable composition within the first end section of in the interior volume of the cladding comprises disposing fuel pellets.
Constructional details · CPC title
Reactors not needing refuelling, i.e. reactors of the type breed-and-burn, e.g. travelling or deflagration wave reactors or seed-blanket reactors · CPC title
by a slip-fit cladding process {by crimping the jacket around the fuel} · CPC title
Details of the construction within the casing · CPC title
Flux flattening · CPC title
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