Micro-reactor fuel sleeve assembly

Patent metadata

Field	Value
Publication number	US-12573509-B2
Application number	US-202318163415-A
Country	US
Kind code	B2
Filing date	Feb 2, 2023
Priority date	Feb 2, 2023
Publication date	Mar 10, 2026
Grant date	Mar 10, 2026

Abstract

Disclosed is nuclear reactor fuel rod for use in a nuclear reactor. The nuclear reactor fuel rod comprises a sleeve defining a longitudinal axis. The sleeve includes a first end portion and a second end portion. The nuclear reactor fuel rod further includes a first end cap mechanically coupled to the first end portion of the sleeve and a second end cap mechanically coupled to the second end portion of the sleeve. The second end cap is configured to slide along the longitudinal axis relative to the sleeve. The nuclear reactor fuel rod further includes a fuel compact located inside of the sleeve between the first end cap and the second end cap.

First claim

What is claimed is:

1. A nuclear reactor fuel rod for use in a nuclear reactor, the nuclear reactor fuel rod comprising:
a sleeve defining a longitudinal axis, the sleeve comprising:
a first end portion; and
a second end portion;

a first end cap mechanically coupled to the first end portion of the sleeve;
a second end cap mechanically coupled to the second end portion of the sleeve, wherein the second end cap is configured to slide along the longitudinal axis relative to the sleeve during operation of the nuclear reactor; and
a fuel compact located inside of the sleeve between the first end cap and the second end cap.

2. The nuclear reactor fuel rod of claim 1 , further comprising a reflector material located inside of the sleeve and between the fuel compact and the second end cap.

3. The nuclear reactor fuel rod of claim 2 , wherein the reflector material is a first reflector material, and wherein the nuclear reactor fuel rod further comprises a second reflector material located inside of the sleeve and between the fuel compact and the first end cap.

4. The nuclear reactor fuel rod of claim 1 , wherein the second end cap comprises:
an end cap end portion; and
a biasing member attached to the end cap end portion.

5. The nuclear reactor fuel rod of claim 4 , wherein the nuclear reactor fuel rod is transitionable from an uncompressed configuration to a compressed configuration, wherein the nuclear reactor fuel rod is in the compressed configuration inside of the nuclear reactor, and wherein in the compressed configuration the biasing member is configured to apply a force to the second end cap thereby compressing the fuel compact.

6. The nuclear reactor fuel rod of claim 1 , wherein the sleeve comprises a slot located at the second end portion, and wherein the second end cap comprises a retention pin that is configured to slide in the slot.

7. The nuclear reactor fuel rod of claim 1 , wherein the second end cap comprises:
a slot; and
a retention pin inserted through the slot, wherein the retention pin is attached to the sleeve at the second end portion, and wherein the second end cap is configured to slide relative to the sleeve.

8. The nuclear reactor fuel rod of claim 1 , wherein the sleeve comprises a slot running along the longitudinal axis of the sleeve from the first end to the second end.

9. The nuclear reactor fuel rod of claim 1 , wherein the second end cap comprises an extraction tool interface feature.

10. The nuclear reactor fuel rod of claim 9 , wherein the extraction tool interface feature is configured to mechanically couple to an extraction tool to insert the fuel rod into the nuclear reactor or to extract the fuel rod from the nuclear reactor.

11. The nuclear reactor fuel rod of claim 9 , wherein the extraction tool interface feature is defined by an internal cavity in the second end cap.

12. The nuclear reactor fuel rod of claim 9 , wherein the extraction tool interface feature extends outward from the second end cap.

13. A nuclear reactor fuel rod for use in a nuclear reactor, the nuclear reactor fuel rod comprising:
a tube defining a longitudinal axis, the tube comprising:
a first end portion; and
a second end portion;

a first end cap mechanically coupled to the first end portion of the tube;
a second end cap comprising an extraction tool interface feature, wherein the second end cap is mechanically coupled to the second end portion of the tube, and wherein the second end cap is configured to move along the longitudinal axis relative to the tube during operation of the nuclear reactor; and
a plurality of fuel pellets located inside of the tube between the first end cap and the second end cap.

14. The nuclear reactor fuel rod of claim 13 , wherein the nuclear reactor fuel rod further comprises a biasing member configured to compress the plurality of fuel pellets.

15. The nuclear reactor fuel rod of claim 13 , further comprising a reflector material located inside of the tube and between the plurality of fuel pellets and the second end cap.

16. The nuclear reactor fuel rod of claim 15 , wherein the reflector material is a first reflector material, and wherein the nuclear reactor fuel rod further comprises a second reflector material located inside of the tube and between the plurality of fuel pellets and the first end cap.

17. The nuclear reactor fuel rod of claim 13 , wherein the tube comprises a slot running along the longitudinal axis of the tube from the first end to the second end.

Assignees

• Westinghouse Electric Co Llc

Inventors

• Shoup Jeffrey
• Aleshin Yuriy
• Gross David M
• Donovan Joshua J
• Van Wyk Jurie J
• Parks Jeffrey M

Classifications

• G21C3/14

  Means forming part of the element for inserting it into, or removing it from, the core; Means for coupling adjacent elements {, e.g. to form a stringer} · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title

• G21C3/045

  Pellets · CPC title

• G21C3/10 Primary

  End closures {; Means for tight mounting therefor} · CPC title