Methods of forming fuel rods comprising porous fuel materials

Patent metadata

Field	Value
Publication number	US-11183309-B2
Application number	US-201816220661-A
Country	US
Kind code	B2
Filing date	Dec 14, 2018
Priority date	Dec 26, 2017
Publication date	Nov 23, 2021
Grant date	Nov 23, 2021

Abstract

A method of forming a fuel rod for a nuclear reactor comprises disposing a powder comprising particles of a fuel material on a substrate, exposing the powder to energy from an energy source to form a first layer of a nuclear fuel, the first layer comprising inter-granular bonds between the particles of the fuel material, disposing additional powder comprising particles of the fuel material over the first layer of the nuclear fuel, and exposing the additional powder to energy from the energy source to form a second layer of the nuclear fuel and to form the nuclear fuel to have a void fraction greater than about 0.20, the second layer comprising inter-granular bonds between the additional powder and the first layer of the nuclear fuel. Related nuclear fuels comprising a porous structure, fuel rods, nuclear reactors, and methods are disclosed.

First claim

What is claimed is:

1. A method of forming a fuel rod for a nuclear reactor, the method comprising:
disposing a powder comprising particles of a fuel material on a substrate;
exposing the powder to energy from an energy source to form a first layer of a nuclear fuel comprising inter-granular bonds between adjacent particles of the fuel material in the first layer;
disposing additional powder comprising particles of the fuel material over the first layer of the nuclear fuel; and
exposing the additional powder to energy from the energy source to form a second layer of the nuclear fuel comprising inter-granular bonds between adjacent particles of the additional powder and between particles of the additional powder and the first layer of the nuclear fuel to form the nuclear fuel to have a void fraction greater than about 0.20.

2. The method of claim 1 , further comprising:
disposing a powder comprising particles of a cladding material around the powder comprising particles of the fuel material; and
exposing the particles of the cladding material to energy from the energy source to form cladding around the nuclear fuel.

3. The method of claim 2 , further comprising exposing the cladding and the nuclear fuel to annealing conditions to densify the cladding without densifying the nuclear fuel.

4. The method of claim 1 , wherein disposing a powder comprising particles of a fuel material on a substrate comprises disposing a powder comprising between 1.0 weight percent and 15.0 weight percent uranium and between 85.0 weight percent and 99.0 weight percent zirconium on the substrate.

5. The method of claim 1 , wherein disposing additional powder comprising particles of the fuel material over the first layer of the nuclear fuel comprises disposing additional powder comprising a different composition of the fuel material than the powder of the first layer of the nuclear fuel.

6. The method of claim 5 , wherein exposing the additional powder to energy from the energy source to form a second layer of the nuclear fuel comprises forming the second layer to have a different composition than the first layer.

7. The method of claim 6 , wherein exposing the additional powder to energy from the energy source to form a second layer of the nuclear fuel comprises forming the first layer to comprise a different amount of enriched nuclear fuel than the second layer.

8. The method of claim 1 , further comprising exposing the nuclear fuel to annealing conditions to densify at least a portion of the nuclear fuel.

9. The method of claim 8 , wherein exposing the nuclear fuel to annealing conditions comprises exposing the nuclear fuel to at least one of a spark plasma sintering process or a hot isostatic pressing process.

10. The method of claim 1 , wherein disposing a powder comprising particles of a fuel material on a substrate comprises disposing a powder comprising particles of the fuel material and particles of a burnable poison material on the substrate.

11. The method of claim 1 , further comprising disposing particles of a diffusion barrier material on the substrate, wherein exposing the powder to energy from an energy source to form a first layer of a nuclear fuel comprises exposing the particles of the diffusion barrier material to energy from the energy source to form a diffusion barrier around the fuel material.

12. The method of claim 1 , wherein disposing a powder comprising particles of a fuel material on a substrate comprises disposing a powder comprising particles of the fuel material and at least one dopant on the substrate.

13. The method of claim 12 , wherein disposing a powder comprising particles of the fuel material and at least one dopant on the substrate comprises disposing a powder comprising particles of the fuel material and at least one dopant selected from the group consisting of carbon nanotubes, zirconium oxide, aluminum oxide, and combinations thereof on the substrate.

14. The method of claim 1 , wherein disposing a powder comprising particles of a fuel material on a substrate comprises disposing a powder comprising particles of uranium and zirconium on the substrate.

15. The method of claim 1 , wherein exposing the powder to energy from an energy source to form a first layer of a nuclear fuel comprises forming the first layer of the nuclear fuel to define an aperture through a central portion of the first layer of the nuclear fuel.

16. The method of claim 1 , wherein disposing a powder comprising particles of a fuel material on a substrate comprises disposing a powder comprising about 10 atomic percent uranium and about 90 atomic percent of at least one of zirconium and tungsten on the substrate.

17. The method of claim 1 , wherein exposing the powder to energy from an energy source to form a first layer of a nuclear fuel comprises forming the first layer of the nuclear fuel to exhibit a composition varying with a radial distance from a center of the first layer.

18. The method of claim 1 , further comprising disposing a powder comprising particles of a cladding material around the powder comprising particles of the fuel material, an enrichment of the nuclear fuel greater proximate the cladding material than at portions distal from the cladding material.

19. The method of claim 1 , wherein exposing the powder to energy from an energy source to form a first layer of a nuclear fuel comprises exposing the powder to energy to form a first layer of an article comprising a bundle of fuel rods.

20. A method of forming a portion of a nuclear reactor, the method comprising:
exposing powder comprising at least a nuclear fuel material and a cladding material to energy to form a first layer of an article;
disposing additional powder over the first layer of the article to form a layer of the additional powder over the first layer of the article; and
exposing the additional powder to energy to form a second layer of the article, wherein the second layer of the article has a same cross-sectional shape as the first layer of the article, the same cross-sectional shape being rotationally offset from the first layer of the article.

21. The method of claim 20 , wherein exposing a powder comprising at least a nuclear fuel material and a cladding material to energy to form a first layer of an article comprises forming the first layer of the article to have a theoretical density less than about 90% theoretical density.

22. The method of claim 20 , wherein exposing powder comprising at least a nuclear fuel material and a cladding material to energy to form a first layer of an article comprises exposing a powder comprising uranium and at least one of a metal oxide and carbon nanotubes to the energy.

23. The method of claim 20 , wherein exposing powder comprising at least a nuclear fuel material and a cladding material to energy to form a first layer of an article comprises exposing a powder comprising at least a nuclear fuel material and a cladding material to energy to form a first layer of an article comprising a bundle of fuel rods.

Assignees

• Battelle Energy Alliance Llc

Inventors

• O'Brien Robert C

Classifications

• G21C3/623

  Oxide fuels · CPC title

• G21C3/20

  with coating on fuel or on inside of casing; with non-active interlayer between casing and active material {with multiple casings or multiple active layers} · CPC title

• G21C3/60

  Metallic fuel; Intermetallic dispersions · CPC title

• G21C3/044 Primary

  Fuel elements with porous or capillary structure · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title