Nuclear fuel rod having cladding with varying diameter

Patent metadata

Field	Value
Publication number	US-12437884-B2
Application number	US-202117324904-A
Country	US
Kind code	B2
Filing date	May 19, 2021
Priority date	May 19, 2021
Publication date	Oct 7, 2025
Grant date	Oct 7, 2025

Abstract

A variable diameter fuel rod of a nuclear reactor assembly is disclosed. The variable diameter fuel rod includes an elongated cladding tube configured to house a plurality of fuel pellets including a fissile material arranged in a fuel stack orientation. The elongated cladding tube includes first and second axial reflector regions and a middle axial region therebetween. The middle axial region comprises an outer diameter defined as d 1 . The first and second axial reflector regions include an outer cladding diameter defined as d 2 and d 3 , respectively. The variable diameter fuel rod further includes a transitional region between the diameter d 1 of the middle axial region and the diameter d 2 of the axial reflector region. The diameter d 2 of the axial reflector region is greater than the diameter d 1 of the middle axial region.

First claim

What is claimed is:

1. A variable diameter fuel rod of a nuclear reactor assembly, the variable diameter fuel rod comprising:
a sealed elongated cladding tube; and
a plurality of fuel pellets positioned within the elongated cladding tube, wherein the plurality of fuel pellets comprise:
a plurality of solid fuel pellets; and
a plurality of annular fuel pellets, wherein an outside diameter of each of the plurality of solid fuel pellets and an outside diameter of each of the plurality of annular fuel pellets is the same, and wherein the sealed elongated cladding tube comprises:
an axial region, wherein the plurality of solid fuel pellets are positioned in the axial region; and
an axial reflector region positioned above the axial region, wherein the plurality of annular fuel pellets are positioned in the axial reflector region, wherein neutrons are reflected by the plurality of annular fuel pellets to the axial region, wherein the sealed elongated cladding tube defines a first inner cladding diameter di 1 along the entire axial region and a second inner cladding diameter di 2 at a top end of the axial reflector region, wherein the second inner cladding diameter di 2 is greater than the first inner cladding diameter di 1 , and wherein the axial reflector region defines a sloped surface of the sealed elongated cladding tube between the first inner cladding diameter di 1 and the second inner cladding diameter di 2 , wherein a first annular gap is defined between the outside diameter of a first annular fuel pellet of the plurality of annular fuel pellets and the sloped surface of the sealed elongated cladding tube, wherein a second annular gap is defined between the outside diameter of a second annular fuel pellet of the plurality of annular fuel pellets and the sloped surface of the sealed elongated cladding tube, wherein the first annular gap is positioned above the second annular gap, and wherein the first annular gap is larger than the second annular gap.

2. The variable diameter fuel rod of claim 1 , wherein a thickness of the sealed elongated cladding tube is the same in the axial region and the axial reflector region.

3. The variable diameter fuel rod of claim 1 , wherein the axial reflector region defines a void volume based on a difference in volume between an internal volume of the axial reflector region and a volume of the plurality of annular fuel pellets positioned in the axial reflector region.

4. The variable diameter fuel rod of claim 1 , wherein the plurality of solid fuel pellets extend along the entire axial length of the axial region.

5. The variable diameter fuel rod of claim 4 , wherein the plurality of annular fuel pellets extend along the entire axial length of the axial reflector region.

6. A variable diameter fuel rod of a nuclear reactor assembly, the variable diameter fuel rod comprising:
a sealed elongate cladding tube, comprising:
a top end;
a bottom end;
an axial reflector region adjacent the top end; and
an axial region positioned below the axial reflector region;

a plurality of solid fuel pellets positioned in the axial region;
a plurality of annular fuel pellets positioned in the axial reflector region, wherein an outside diameter of each of the plurality of solid fuel pellets and an outside diameter of each of the plurality of annular fuel pellets is the same, wherein neutrons are reflected by the plurality of annular fuel pellets to the axial region, and wherein the plurality of annular fuel pellets comprise:
a first annular fuel pellet adjacent the top end of the sealed elongate cladding tube; and
a second annular fuel pellet positioned below the first annular fuel pellet;

a first annular gap defined between the outside diameter of the first annular fuel pellet and a first inner cladding diameter defined by the sealed elongate cladding tube in the axial reflector region; and
a second annular gap defined between the outside diameter of the second annular fuel pellet and a second inner cladding diameter defined by the sealed elongate cladding tube in the axial reflector region, wherein the first annular gap is larger than the second annular gap.

7. The variable diameter fuel rod of claim 6 , wherein the first annular gap is positioned above the second annular gap.

8. The variable diameter fuel rod of claim 6 , wherein a thickness of the sealed elongate cladding tube is the same in the axial region and the axial reflector region.

9. A variable diameter fuel rod of a nuclear reactor assembly, the variable diameter fuel rod comprising:
a sealed elongate cladding tube, comprising:
a top end;
a bottom end;
an axial reflector region adjacent the top end; and
an axial region positioned below the axial reflector region;

a first plurality of fuel pellets positioned in the axial region;
a second plurality of fuel pellets positioned in the axial reflector region, wherein neutrons are reflected by the second plurality of fuel pellets to the axial region, wherein the second plurality of fuel pellets are stacked on top of each other in a fuel pellet stack extending along the entire axial length of the axial reflector region, and wherein the fuel pellet stack defines an outside diameter;
a first annular gap defined between the outside diameter of the fuel pellet stack and a first inner cladding diameter defined by the sealed elongate cladding tube in the axial reflector region; and
a second annular gap defined between the fuel pellet stack and a second inner cladding diameter defined by the sealed elongate cladding tube in the axial reflector region, wherein the first annular gap is larger than the second annular gap, and wherein the first annular gap is positioned above the second annular gap.

10. The variable diameter fuel rod of claim 9 , wherein at least one of the second plurality of fuel pellets is an annular fuel pellet.

11. The variable diameter fuel rod of claim 9 , wherein a thickness of the sealed elongate cladding tube is the same in the axial region and the axial reflector region.

Assignees

• Westinghouse Electric Co Llc

Inventors

• Guler Cenk
• Sung Yixing

Classifications

• G21C3/17

  Means for storage or immobilisation of gases in fuel elements · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title

• G21C7/28

  by displacement of the reflector or parts thereof · CPC title

• G21C3/06 Primary

  Casings; Jackets · CPC title

• G21C3/3213

  Means for the storage or removal of fission gases (means for the storage of fission gases in the elements G21C3/16; means for the removal of fission gases from elements G21C3/04) · CPC title