Fuel element with multi-smear density fuel

Patent metadata

Field	Value
Publication number	US-11990249-B2
Application number	US-201916518890-A
Country	US
Kind code	B2
Filing date	Jul 22, 2019
Priority date	Aug 27, 2015
Publication date	May 21, 2024
Grant date	May 21, 2024

Abstract

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.

First claim

What is claimed is:

1. A method of manufacturing a fuel element, the method comprising:
modeling fuel strain along a longitudinal axis of a fuel element;
modeling a smear density profile along the longitudinal axis of the fuel element to offset the modeled fuel strain such that at least one region of locally decreased strain corresponds to a region of locally increased smear density wherein the smear density profile approximates an inverted Gaussian shape and wherein the fuel element comprises twelve zones and at least three sections, the first section proximate a first longitudinal end of the fuel element, a third section proximate a second longitudinal end of the fuel element, and a second section between the first and third sections, wherein an average smear density of the first section is greater than an average smear density of the second section, wherein an average smear density of the third section is greater than the smear density of the second section, and wherein the first section comprises five zones and the smear density profile of the zones of the first section varies according to a decreasing step function, wherein the second section comprises two zones and the smear density profile of the zones of the second section is constant, and wherein a third section comprises five zones and the smear density profile of the zones of the third section varies according to an increasing step function; and
constructing the fuel element to have a tubular interior volume storing a fissionable composition, the fissionable composition in thermal transfer contact with an interior surface of the fuel element and having at least five different smear densities that vary along the longitudinal axis of the fuel element based on the modeled smear density profile.

2. The method of claim 1 , wherein the smear density profile increases an average burnup of the fuel element.

3. The method of claim 1 , wherein the smear density of the fuel element is higher at a first end of the fuel element than at a second opposite end of the fuel element.

4. The method of claim 3 , wherein the first end of the fuel element is proximate a coolant entry point within a fuel assembly and the second opposite end of the fuel element is proximate a coolant exit point of the fuel assembly.

5. The method of claim 1 , wherein the modeled smear density profile includes regions of increased smear density that correspond to regions of decreased neutron flux in the fuel element.

6. The method of claim 1 , wherein constructing the fuel element further comprises constructing the fuel element to have a variable cladding thickness along the longitudinal axis to offset to offset the modeled fuel strain.

7. The method of claim 1 , wherein constructing the fuel element further comprises:
disposing a first fissionable composition within a first end section of the tubular interior volume, the first fissionable composition having a first average smear density;
disposing a second fissionable composition within a central section of the tubular interior volume, the second fissionable composition having a second average smear density less than the first average smear density; and
disposing a third fissionable composition within a second end section of the tubular interior volume, the third fissionable composition having a third average smear density greater than the second average smear density.

8. The method of claim 7 , wherein the first end section and the second end section are equal length, and the first average smear density is greater than the third average smear density.

9. The method of claim 7 , 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 third fissionable composition varies according to an increasing step function within the second end section.

10. The method of claim 7 , 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.

11. The method of claim 1 , wherein smear density varies according to a step function.

12. The method of claim 7 , wherein disposing a first fissionable composition within the first end section of the tubular interior volume comprises disposing a fissionable metal sponge.

13. The method of claim 7 , wherein disposing a first fissionable composition within the first end section of in the tubular interior volume of comprises disposing fuel pellets.

Assignees

• Terrapower Llc

Inventors

• Cheatham Iii Jesse R
• Latta Ryan N
• Miller Samuel J

Classifications

• G21C3/04 Primary

  Constructional details · CPC title

• G21C1/026

  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

• G21C3/16

  Details of the construction within the casing · CPC title

• G21C7/005

  Flux flattening · CPC title

• G21C21/08

  by a slip-fit cladding process {by crimping the jacket around the fuel} · CPC title