Nuclear reactor fuel rod and fuel assembly having bundled same

Patent metadata

Field	Value
Publication number	US-10796807-B2
Application number	US-201415529663-A
Country	US
Kind code	B2
Filing date	Nov 26, 2014
Priority date	Nov 26, 2014
Publication date	Oct 6, 2020
Grant date	Oct 6, 2020

Abstract

A nuclear reactor fuel rod is a fuel rod for a light-water reactor. The nuclear reactor fuel rod includes a fuel cladding tube and an end plug, both of which are formed of a silicon carbide material. A bonding portion between the fuel cladding tube and the end plug is formed by brazing with a predetermined metal bonding material interposed, and/or by diffusion bonding. The predetermined metal bonding material has a solidus temperature of 1200° C. or higher. An outer surface of the bonding portion, and a portion of an outer surface of the fuel cladding tube and the end plug, which is adjacent to the outer surface of the bonding portion are covered by bonding-portion coating formed of a predetermined coating metal. The predetermined metal bonding material and the predetermined coating metal have an average linear expansion coefficient which is less than 10 ppm/K.

First claim

The invention claimed is:

1. A nuclear reactor fuel rod for light-water reactor, comprising:
a fuel cladding tube; and
an end plug, the end plug having an insertion straight body portion and a butting surface, the insertion straight body portion being inserted into the fuel cladding tube, the butting surface butts with an end surface of the fuel cladding tube,
wherein both of the fuel cladding tube and the end plug are composed of a silicon carbide material,
a bonding portion between the fuel cladding tube and the end plug is formed by brazing and/or by diffusion bonding with a predetermined metal bonding material interposed, the predetermined metal bonding material having a solidus temperature of 1200° C. or higher,
an outer surface of the bonding portion, and a portion of an outer surface of the fuel cladding tube and the end plug, which is adjacent to the outer surface of the bonding portion are covered by bonding-portion coating formed of a predetermined coating metal, and
the predetermined metal bonding material and the predetermined coating metal have an average linear expansion coefficient which is less than 10 ppm/K.

2. The nuclear reactor fuel rod according to claim 1 ,
wherein the predetermined metal bonding material is one selected from silicon, a silicon alloy, titanium, a titanium alloy, zirconium, and a zirconium alloy, and
the predetermined coating metal is one selected from titanium, a titanium alloy, zirconium, and a zirconium alloy.

3. The nuclear reactor fuel rod according to claim 1 ,
wherein a thickness of the bonding-portion coating is 0.1 mm to 1 mm.

4. The nuclear reactor fuel rod according to claim 1 ,
wherein the silicon carbide material is a silicon carbide fiber-reinforced silicon carbide composite material obtained by composing silicon carbide fiber in a matrix of silicon carbide.

5. The nuclear reactor fuel rod according to claim 4 ,
wherein the silicon carbide material is a material in which a silicon carbide layer is further formed at a portion of a surface of the silicon carbide fiber-reinforced silicon carbide composite material.

6. The nuclear reactor fuel rod according to claim 1 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

7. The nuclear reactor fuel rod according to claim 1 ,
wherein the fuel cladding tube and the end plug are fastened further by a screw structure.

8. The nuclear reactor fuel rod according to claim 2 ,
wherein a thickness of the bonding-portion coating is 0.1 mm to 1 mm.

9. The nuclear reactor fuel rod according to claim 2 ,
wherein the silicon carbide material is a silicon carbide fiber-reinforced silicon carbide composite material obtained by composing silicon carbide fiber in a matrix of silicon carbide.

10. The nuclear reactor fuel rod according to claim 3 , wherein the silicon carbide material is a silicon carbide fiber-reinforced silicon carbide composite material obtained by composing silicon carbide fiber in a matrix of silicon carbide.

11. The nuclear reactor fuel rod according to claim 8 ,
wherein the silicon carbide material is a silicon carbide fiber-reinforced silicon carbide composite material obtained by composing silicon carbide fiber in a matrix of silicon carbide.

12. The nuclear reactor fuel rod according to claim 9 ,
wherein the silicon carbide material is a material in which a silicon carbide layer is further formed at a portion of a surface of the silicon carbide fiber-reinforced silicon carbide composite material.

13. The nuclear reactor fuel rod according to claim 10 ,
wherein the silicon carbide material is a material in which a silicon carbide layer is further formed at a portion of a surface of the silicon carbide fiber-reinforced silicon carbide composite material.

14. The nuclear reactor fuel rod according to claim 11 ,
wherein the silicon carbide material is a material in which a silicon carbide layer is further formed at a portion of a surface of the silicon carbide fiber-reinforced silicon carbide composite material.

15. The nuclear reactor fuel rod according to claim 2 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

16. The nuclear reactor fuel rod according to claim 3 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

17. The nuclear reactor fuel rod according to claim 4 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

18. The nuclear reactor fuel rod according to claim 5 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

19. The nuclear reactor fuel rod according to claim 8 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

20. The nuclear reactor fuel rod according to claim 9 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

21. The nuclear reactor fuel rod according to claim 10 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

22. The nuclear reactor fuel rod according to claim 11 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

23. The nuclear reactor fuel rod according to claim 12 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

24. The nuclear reactor fuel rod according to claim 13 ,
wherein the butting surface between the fuel cladding tube and the end plug at the bonding portion is formed to cause a direction paralleled with the butting surface to be inclined to an axial direction of the fuel cladding tube at an angle of 5° to 60°.

25. The nuclear reactor fuel rod according to claim 14 ,
wherein the butting surface between the f

Assignees

• Hitachi Ltd

Inventors

• ISHIBASHI Ryou
• Aota Kinya
• Zhang Xudong
• Kita Hideki
• Yamashita Seiji

Classifications

• C04B2237/127

  The active component for bonding being a refractory metal · CPC title

• C04B2237/16

  Silicon interlayers · CPC title

• C04B2237/765

  at least one member being a tube · CPC title

• C04B2237/365

  Silicon carbide · CPC title

• G21C21/02

  Manufacture of fuel elements or breeder elements contained in non-active casings · CPC title